6,289
Views
130
CrossRef citations to date
0
Altmetric
50TH ANNIVERSARY INVITED REVIEW

Current understanding of radiation-induced degradation in light water reactor structural materials

Pages 213-254 | Received 28 Sep 2012, Accepted 12 Dec 2012, Published online: 15 Mar 2013

References

  • Odette , G R and Lucas , G E . 1998 . Recent progress in understanding reactor pressure vessel steel embrittlement . Rad Effects Defects Solids , 144 : 189 – 231 . doi: 10.1080/10420159808229676
  • Odette , G R and Nanstad , R K . 2009 . Predictive reactor pressure vessel steel irradiation embrittlement model: issues and opportunities . J Metals , 61 : 17 – 23 .
  • Phythian , W J and English , C A . 1993 . Microstructural evolution in reactor pressure vessel steels . J Nucl Mater , 205 : 162 – 177 . doi: 10.1016/0022-3115(93)90079-E
  • Scott , P. 1994 . A review of irradiation assisted stress corrosion cracking . J Nucl Mater , 211 : 101 – 122 . doi: 10.1016/0022-3115(94)90360-3
  • Bruemmer , S M , Simonen , E P , Scott , P M , Andresen , P L , Was , G S and Nelson , J L . Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals . J Nucl Mater , 274 299 – 314 . doi: 10.1016/S0022-3115(99)00075-6
  • Was , G S and Andresen , P L . 2007 . Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments . Corrosion , 63 : 19 – 45 . doi: 10.5006/1.3278331
  • Chopra , O K and Rao , A S . 2011 . A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels . J Nucl Mater , 409 : 235 – 256 . doi: 10.1016/j.jnucmat.2010.12.001
  • Fukuya , K , Nakata , H , Kimura , I , Ohmura , M , Kitagawa , Y , Ito , T and Shin , K . 2003 . “ Three dimensional radiation transport analyses in PWR with TORT and MCNP ” . In Proceedings of the 11th International Symposium on Reactor Dosimetry , Singapore : World Scientific .
  • Matsuzawa , H . 2009 . “ Prediction of radiation embrittlement for highly irradiated reactor pressure vessel steels ” . In Proceedings of the ASME 2009 Pressure Vessel and Piping Division Conference , ASME . PVP2009-78096
  • Yamashita , N , Iwasaki , M , Dozaki , K and Soneda , N . 2009 . “ Industry practice for the neutron irradiation embrittlement of reactor pressure vessel steels in Japan ” . In Proceedings of the 17th International Conference on Nuclear Engineering , ASME . ICONE17-75322
  • Chaouadi , R and Gerard , R . 2005 . Copper precipitate hardening of irradiated RPV materials and implications on the superposition law and re-irradiation kinetics . J Nucl Mater , 345 : 65 – 74 . doi: 10.1016/j.jnucmat.2005.05.001
  • Hawthorne , J R . 1982 . “ Significance of nickel and copper content to radiation sensitivity and postirradiation heat treatment recovery of reactor vessel steels ” . In Effects Radiation Materials: ASTM STP 782 , 372 – 391 . ASTM .
  • Williams , T J . 2004 . The effect of nickel, manganese and copper on the irradiated sensitivity of low alloy steel welds . Int J Pres Vessel Piping , 81 : 657 – 665 . doi: 10.1016/j.ijpvp.2004.02.005
  • Stofanak , R J , Li , Y Y , Burke , M G and Matuszyk , K . 2001 . “ Irradiation embrittlement behavior of high strength low alloy steels containing about 3.3% nickel ” . In Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , NACE . [CD-ROM]
  • Wire , G L , Beggs , W J and Leax , T R . 2004 . “ Evaluation of irradiated embrittlement of A508 Gr4N and comparison to other low-alloy steels ” . In Effects of Radiation on Materials: 21st International Symposium, ASTM STP 1447 , 179 – 193 . ASTM .
  • Shibamoto , H , Kitao , T , Matsui , H , Hasegawa , M , Yamaguchi , S and Kimura , A . 2002 . “ Effect of nickel in irradiation hardening and microstructure evolution of proton irradiated Fe-Cu alloy ” . In Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405 , 722 – 733 . ASTM .
  • Odette , G R , Yamamoto , T , Eason , E D and Nastad , R K . 2007 . “ On the metallurgical and irradiation variable dependence of the embrittlement of RPV steels ” . In Proceedings of the International Symposium on Research for Aging Management of Light Water Reactors , 279 – 306 . INSS .
  • Burke , M G , Stofanak , R J , Hyde , J. M , English , C A and Server , W L . 2004 . Microstructural aspects of irradiation damage in A508Gr 4N forging steel: composition and flux effects . J ASTM Int , 1 : JAI11773 doi: 10.1520/JAI11773
  • Yabuuchi , K , Saito , M , Kasada , R and Kimura , A . 2011 . Neutron irradiation hardening and microstructural changes in Fe-Mn binary alloys . J Nucl Mater , 414 : 498 – 502 . doi: 10.1016/j.jnucmat.2011.05.008
  • Beaven , P A , Frisius , F , Kampmann , R , Wagner , R and Hawthorne , J R . 1989 . “ SANS investigation of irradiated A533-B steels doped with phosphorus ” . In Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Third Volume), ASTM STP 1011 , 243 – 256 . ASTM .
  • Buswell , J T , Little , E A and Sinclair , R L . 1999 . “ An analysis of radiation effects in model A533B pressure vessel steels containing copper, phosphorus and nickel additions ” . In Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325 , 30 – 51 . ASTM .
  • McElroy , R J and Lowe , A L Jr . 1996 . “ Irradiation embrittlement modelling of Linde 80 weld metals ” . In Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1270 , 68 – 85 . ASTM .
  • Suzuki , T. , Itoh , K , Naruse , Y , Matsui , H and Kimura , A . 2000 . “ Effect of location of V-notch on neutron irradiation-induced shift in DBTT of HAZ of welded pressure vessel steel ” . In Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366 , 266 – 278 . ASTM .
  • Katsuyama , J , Tobita , T , Nishiyama , Y and Onizawa , K . 2012 . Mechanical and microstructural characterization of heat-affected zone materials of reactor pressure vessel . J Press Vessel Technol , 134 : 031402 doi: 10.1115/1.4005868
  • Suzuki , M , Onizawa , K and Kizaki , M . 1996 . “ Effects of neutron flux and irradiation temperature on irradiation embrittlement of A533B steels ” . In Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270 , 351 – 362 . ASTM .
  • Murakami , K , Abe , H , Iwai , T , Tamura , S , Katano , Y , Iwata , T , Nishida , T and Sekimura , N . 2009 . “ Effect of microstructure on ion-irradiation-induced hardening in A533B model alloys at 563K ” . In Proceedings of the 2009 International Congress on Advances in Nuclear Power Plants (ICAPP ‘09) Tokyo May 10–14 Paper 9453
  • Jones , R B and Williams , T J . 1996 . “ The dependence of radiation hardening and embrittlement on irradiation temperature ” . In Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270 , 569 – 590 . ASTM .
  • Williams , T J , Burch , P R , English , C A and de la cour Ray , P HN . 1988 . “ The effect of irradiation dose rate and temperature, and copper and nickel content on the irradiation shift of low alloy steel submerged arc welds ” . In Proceedings of the 3rd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 121 – 131 . TMS .
  • 2001 . “ Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials ” . In Conference Proceedings, EPRI 1006981, CRIEPI T980203 Olympic Valley , CA November 12–14, 2001; [CD-ROM]
  • Stoller , R E . 1993 . “ The influence of damage rate and irradiation temperature on radiation-induced embrittlement in pressure vessel steels ” . In Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175 , 394 – 423 . ASTM .
  • Stoller , R E . 2004 . The effect of neutron flux on radiation-induced embrittlement in reactor pressure vessel steels . J ASTM Int , 1 : JAI11355 doi: 10.1520/JAI11355
  • Asano , K , Nishiyama , T , Soneda , N , Dohi , K , Nishida , K , Nomoto , A , Ohta , T , Ishimaru , Y , Yoneda , H , Iida , J and Yuya , H . 2010 . “ Current understandings on the neutron irradiation embrittlement of BWR reactor pressure vessel steels in Japan ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , A123 SFEN . [CD-ROM]
  • Soneda , N , Dohi , K , Nishida , K , Nomoto , A , Iwasaki , M , Tsuno , S , Akiyama , T , Watanabe , S and Ohta , T . 2010 . “ Flux effect on neutron irradiation embrittlement of reactor pressure vessel steels irradiated to high fluences ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , A080 SFEN . [CD-ROM]
  • Remec , I , Wang , J A , Kam , F BK and Farrell , K . 1994 . Effects of gamma-induced displacements on HFIR pressure vessel materials . J Nucl Mater , 217 : 258 – 268 . doi: 10.1016/0022-3115(94)90375-1
  • Fukuya , K and Kimura , I . 2003 . Calculation of gamma induced displacement cross-sections of iron considering positron contribution and using standard damage model . J Nucl Sci Technol , 40 : 423 – 428 . doi: 10.1080/18811248.2003.9715375
  • Fujii , K , Fukuya , K , Nakata , H , Hono , K , Nagai , Y and Hasegawa , M . 2005 . Hardening and microstructural evolution in A533B steels under high-dose electron irradiation . J Nucl Mater , 340 : 247 – 258 . doi: 10.1016/j.jnucmat.2004.12.008
  • Fujii , K , Nakata , H , Fukuya , K , Ohkubo , T , Hono , K , Nagai , Y , Hasegawa , M and Yoshiie , T . 2010 . Hardening and microstructural evolution in A533B steels under neutron irradiation and a direct comparison with electron irradiation . J Nucl Mater , 400 : 46 – 55 . doi: 10.1016/j.jnucmat.2010.02.008
  • Farrell , K , Stoller , R E , Jung , P and Ullmaier , H . 2000 . Hardening of ferritic alloys at 288ºC by electron irradiation . J Nucl Mater , 279 : 77 – 83 . doi: 10.1016/S0022-3115(99)00270-6
  • Odette , G R , Lucas , G E and Klingensmith , D . 1999 . “ Irradiation hardening of pressure vessel steels at 60ºC: The role of thermal neutrons and boron ” . In Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325 , 3 – 13 . ASTM .
  • Jones , R B , Edens , D J and Wootton , M R . 2000 . “ Influence of thermal neutrons on the hardening and embrittlement of plate steels ” . In Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366 , 366 – 382 . ASTM .
  • Garner , F A , Greenwood , L R and Roy , P . 1999 . “ An assessment of potential gamma ray enhancement of embrittlement in ABWR pressure vessel walls ” . In Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325 , 52 – 74 . ASTM .
  • Hawthorne , J R and Loss , F J . 1968 . The effects of coupling nuclear radiation with static service stresses on pressure vessel material behavior . Nucl Eng Design , 8 : 108 – 116 . doi: 10.1016/0029-5493(68)90020-4
  • Nichols , R W and Harries , D R . 1963 . “ Brittle fracture and irradiation effects in ferritic pressure vessel steels ” . In Proceedings of the Symposium on Radiation Effects on Metals and Neutron Dosimetry, ASTM STP 341 , 162 – 198 . ASTM .
  • Reynolds , M B . 1963 . The effect of stress on the radiation stability of ASTM A302 grade B pressure-vessel steel . Mater Res Stand , 3 : 644 – 645 .
  • Fujii , K , Fukuya , K , Kasada , R , Kimura , A and Ohkubo , T . 2010 . Effects of stress on radiation hardening and microstructural evolution in A533B steels . J Nucl Mater , 407 : 151 – 157 . doi: 10.1016/j.jnucmat.2010.09.055
  • Watanabe , H , Hiragane , A , Shin , S , Yoshida , N and Kamada , Y . The influence of stress on radiation induced hardening of A533B and Fe-Mn alloys . J Nucl Mater , Forthcoming
  • Lucas , G E , Odette , G R , Lombrozo , P M and Sheckherd , J M . 1985 . “ Effects of composition, microstructure, and temperature on irradiation hardening of pressure vessel steels ” . In Effects of Radiation on Materials: 12th International Symposium, ASTM STP 870 , 900 – 930 . ASTM .
  • Odette , G R . 1995 . Radiation induced microstructural evolution in reactor pressure vessel steels . Mat Res Soc Symp Proc , 373 : 137 – 148 .
  • English , C A , Ortner , S R , Gage , G , Server , W L and Rosinski , S T . 2001 . “ Review of phosphorus segregation and intergranular embrittlement in reactor pressure vessel steels ” . In Effects of radiation on Materials: 20th International Symposium, ASTM STP 1405 , 151 – 173 . ASTM .
  • Nagai , Y , Hasegawa , M , Tang , Z , Hempel , A , Yubuta , K , Shimamura , T , Kawzoe , Y , Kawai , A and Kano , F . 2000 . Positron Confinement in ultrafine embedded particles: Quantum-dot-like state in an Fe-Cu alloy . Phys Rev , B61 : 6574 – 6578 .
  • Auger , P , Pareige , P , Welzel , S and Van Duysen , J-C . 2000 . Synthesis of atom probe experiments on irradiation-induced solute segregation in French ferritic pressure vessel steels . J Nucl Mater , 280 : 331 – 344 . doi: 10.1016/S0022-3115(00)00056-8
  • Huang , H F , Radiguet , B , Pareige , P , Todeschini , R and Chas , G . 2010 . “ Evolution of the microstructure of a French reactor pressure vessel steel under neutron irradiation ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , A073 SFEN . [CD-ROM]
  • Toyama , T , Nagai , Y , Tang , Z , Hasegawa , M , Almazouzi , A , van Walle , E and Gerard , R . 2007 . Nanostructural evolution in surveillance test specimens of a commercial nuclear reactor pressure vessel studied by three-dimensional atom probe and positron annihilation . Acta Mater , 55 : 6852 – 6860 . doi: 10.1016/j.actamat.2007.08.047
  • Gurovich , B , Kuleshova , E , Prikhodko , K and Dedotova , S . 2010 . “ Assessment of the recovery annealing efficiency fro VVER-1000 materials’ structure reset and lifetime extension ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , A009 SFEN . [CD-ROM]
  • Miller , M K , Russel , K F , Kocik , J and Keilova , E . 2000 . Embrittlement of low copper VVER 440 surveillance samples neutron-irradiated to high fluences . J Nucl Mater , 282 : 83 – 88 . doi: 10.1016/S0022-3115(00)00240-3
  • Fukuya , K , Ohno , K , Nakata , H , Dumbill , S and Hyde , J M . 2003 . Microstructural evolution in medium copper low alloy steels irradiated in a pressurized water reactor and a material test reactor . J Nucl Mater , 312 : 163 – 173 . doi: 10.1016/S0022-3115(02)01675-6
  • Fukuya , K , Ohno , K and Nakata , H . 2001 . Microstructural evolution in reactor vessel steels under neutron irradiation . INSS Monographs No.1; INSS , [in Japanese]
  • Soneda , N , Dohi , K , Nomoto , A , Nishida , K and Ishino , S . 2007 . Development of neutron irradiation embrittlement correlation of reactor pressure vessel materials of light water reactors , CRIEPI . Report No.Q06019 [in Japanese]
  • Soneda , N , Dohi , K , Nishida , A and Ishino , S . 2010 . Embrittlement correlation method for the Japanese reactor pressure vessel materials . J ASTM Int , 7 : JAI102127 doi: 10.1520/JAI102127
  • Carter , R , English , C and Server , W . 1997 . “ Prediction of neutron irradiation embrittlement in BWR vessel steels ” . In Proceedings of the International Symposium Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 829 – 842 . SFEN . A058
  • Nagai , Y , Toyama , T , Nishiyama , Y , Suzuki , M , Tang , Z and Hasegawa , M . 2005 . Kinetics of irradiation-induced Cu precipitation in nuclear reactor pressure vessel steels . Appl Phys Lett , 87 : 261920 doi: 10.1063/1.2159091
  • Buswell , J T , Phythian , W J , McElroy , R J , Dumbill , S , Ray , P HN , Mace , J and Sinclair , R N . 1995 . Irradiation-induced microstructural changes and hardening mechanisms in model PWR reactor pressure vessel steels . J Nucl Mater , 225 : 196 – 214 . doi: 10.1016/0022-3115(95)00026-7
  • Kampmann , R , Frisius , F , Hackbarth , H , Beaven , P A , Wagner , R and Hawthorne , J R . 1991 . “ SANS investigation of low alloy steels in neutron irradiated, annealed and reirradiated conditions ” . In Proceedings of the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 679 – 688 . ANS .
  • Williams , T J and Ellis , D . 2001 . “ A mechanistically-based model of irradiation damage in low alloy steel submerged arc welds ” . In Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405 , 8 – 27 . ASTM .
  • Carter , R G , Soneda , N , Dohi , K , Hyde , J M , English , C A and Server , W L . 2001 . Microstructural characterization of irradiated-induced Cu-rich clusters in reactor pressure vessel steels . J Nucl Mater , 298 : 211 – 224 . doi: 10.1016/S0022-3115(01)00659-6
  • Hyde , J M , Ellis , D , English , C A and Williams , T J . 2001 . “ Microstructural evolution in high nickel submerged arc welds ” . In Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405 , 262 – 288 . ASTM .
  • Miller , M K , Russell , K F , Sokolov , M A and Nanstad , R K . 2003 . Atom probe tomography characterization of radiation-sensitive KS-01 weld . J Nucl Mater , 320 : 177 – 183 . doi: 10.1016/S0022-3115(03)00108-9
  • Burke , M G , Stofanak , R J , Hyde , J M , English , C A and Server , W L . 2004 . Microstructural aspects of irradiation damage in A508 Gr4N forging steel: composition and flux effects . J ASTM Int , 1 : JAI12453 doi: 10.1520/JAI11773
  • Bohmert , J , Viehrig , H-W and Ulbricht , A . 2004 . Correlation between irradiation-induced changes of microstructural parameters and mechanical properties of RPV steels . J Nucl Mater , 334 : 71 – 78 . doi: 10.1016/j.jnucmat.2004.05.003
  • Pareige , P , Radiguet , B , Krummeich-Brangier , R , Barbu , A , Zabusov , O and Kozodaev , M . 2005 . Atomic-level observation with three-dimensional atom probe of the solute behaviour in neutron-, ion- or electron-irradiated ferritic alloys . Philo Mag , 85 : 429 – 441 . doi: 10.1080/02678370412331320233
  • Ulbricht , A , Bohmert , J and Viehrig , H-W . 2005 . Microstructural and mechanical characterization of radiation effects in model reactor pressure vessel steels . J ASTM Int , 2 : JAI12385 doi: 10.1520/JAI12385
  • Miller , M K , Russell , K F , Sokolov , M A and Nanstad , R K . 2005 . Atom probe tomography of radiation-sensitive KS-01 weld . Philo Mag , 85 : 401 – 408 . doi: 10.1080/0267837041233132060
  • Miller , M K , Nanstad , R K , Sokolov , M A and Russell , K F . 2006 . The effects of irradiation, annealing and reirradiation on RPV steels . J Nucl Mater , 351 : 216 – 222 . doi: 10.1016/j.jnucmat.2006.02.010
  • Ulbricht , A , Bergner , F , Dewhurst , C D and Heinemann , A . 2006 . Small-angle neutron scattering study of post-irradiation annealed neutron irradiated pressure vessel steels . J Nucl Mater , 353 : 27 – 34 . doi: 10.1016/j.jnucmat.2006.02.083
  • Miller , M K , Russell , K F , Sokolov , M A and Nanstad , R K . 2007 . APT characterization of irradiated high nickel RPV steels . J Nucl Mater , 361 : 248 – 261 . doi: 10.1016/j.jnucmat.2006.12.015
  • Miller , M K and Russel , K F . 2007 . Embrittlement of RPV steels: An atom probe tomography perspective . J Nucl Mater , 371 : 145 – 160 . doi: 10.1016/j.jnucmat.2007.05.003
  • Soneda , N , Dohi , K , Nishida , K , Nomoto , A , Tomimatsu , M and Matsuzawa , H . 2009 . Microstructural characterization of RPV materials irradiated to high fluences at high flux . J ASTM Int , 6 : JAI102128 doi: 10.1520/JAI102128
  • Takeuchi , T , Kuramoto , A , Kameda , J , Toyama , T , Nagai , Y , Hasegawa , M , Ohkubo , T , Yoshiie , T , Nishiyama , Y and Onizawa , K . 2010 . Effects of chemical composition and dose on microstructure evolution and hardening of neutron-irradiated reactor pressure vessel steels . J Nucl Mater , 402 : 93 – 101 . doi: 10.1016/j.jnucmat.2010.04.008
  • Bergner , F , Lambrecht , M , Ulbricht , A and Almazouzi , A . 2010 . Comparative small-angle neutron scattering study of neutron-irradiated Fe, Fe-based alloys and a pressure vessel steel . J Nucl Mater , 399 : 129 – 136 . doi: 10.1016/j.jnucmat.2009.11.011
  • Radiguet , B , Barbu , A and Pareige , P . 2007 . Understanding of copper precipitation under electron or ion irradiations in FeCu0.1wt% ferritic alloy by combination of experiments and modeling . J Nucl Mater , 360 : 104 – 117 . doi: 10.1016/j.jnucmat.2006.09.007
  • Verheyen , K , Jardin , M and Almazouzi , A . 2006 . Coincidence Doppler broadening spectroscopy in Fe, Fe-C and Fe-Cu after neutron irradiation . J Nucl Mater , 351 : 209 – 215 . doi: 10.1016/j.jnucmat.2006.02.011
  • Glade , S C , Wirth , B D , Odette , G R , Asoka-Kumar , P , Sterne , P A and Howell , R H . 2005 . Positron annihilation spectroscopy and small-angle neutron scattering characterization of the effect of Mn on the nanostructural features formed in irradiated Fe-Cu-Mn alloys . Philo Mag , 85 : 629 – 639 . doi: 10.1080/02678370412331320053
  • Yu , Q , Was , G S , Alexander , D and Odette , R . 2001 . “ Hardening and precipitate character in proton irradiated model pressure vessel steel alloys ” . In Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , NACE . [CD-ROM]
  • Hasegawa , M , Nagai , Y , Tang , Z , Kanai , T , Chiba , T , Takenaka , M and Kuramoto , E . 2001 . “ Positron annihilation characterization of ultrafine Cu precipitation and vacancy cluster complexes in thermally aged and neutron-irradiated Fe-Cu model alloys ” . In Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , NACE . [CD-ROM]
  • Fujii , K , Ohkubo , T and Fukuya , K . 2011 . Effects of solute elements on irradiation hardening and microstructural evolution in low alloy steels . J Nucl Mater , 417 : 949 – 952 . doi: 10.1016/j.jnucmat.2010.12.192
  • Meslin , E , Radiguet , B , Pareige , P and Barbu , A . 2010 . Kinetic of solute clustering in neutron irradiated ferritic model alloys and a French pressure vessel steel investigated by atom probe tomography . J Nucl Mater , 399 : 137 – 145 . doi: 10.1016/j.jnucmat.2009.11.012
  • Fujii , K and Fukuya , K . 2008 . “ A study of radiation embrittlement using simulation irradiation ” . In Proceedings of the 16th Pacific Basin Nuclear Conference Aomori October 13-18; Paper ID: P16P1376
  • Hyde , J M , Cerezo , A and Williams , T L . 2009 . Statistical analysis of atom probe data: detecting the early stages of solute clustering and/or co-segregation . Ultramicroscopy , 109 : 502 – 509 . doi: 10.1016/j.ultramic.2008.10.007
  • Jones , R B and Bolton , C J . 1996 . “ Neutron radiation embrittlement studies in support of continued operation and validation of sampling of Magnox reactor steel pressure vessels and components ” . In Proceedings of the 24th Water Reactor Safety Meeting; 21–23 Oct. , Washington : NUREG/CP-0157 .
  • Russell , K C and Brown , L M . 1972 . A dispersion strengthening model based on differing elastic moduli applied to the iron-copper system . Acta Metal , 20 : 969 – 974 . doi: 10.1016/0001-6160(72)90091-0
  • Liu , C L , Odette , G R , Wirth , B D and Lucas , G E . 1997 . A lattice Monte Carlo simulation of nanophase compositions and structures in irradiated pressure vessel Fe-Cu-Ni-Mn-Si steels . Mater Sci Eng , A238 : 202 – 209 .
  • Cerezo , A , Hirosawa , S , Rozdilsky , I and Smith , G DW . 2003 . Combined atomic-scale modelling and experimental studies of nucleation in the solid state . Phil Trans R Soc Lond A , 361 : 463 – 477 . doi: 10.1098/rsta.2002.1139
  • Vincent , E , Becquart , C S and Domain , C . 2008 . Microstructural evolution under high flux irradiation of dilute Fe-CuNiMnSi alloys studied by an atomic kinetic Monte Carlo model accounting for both vacancies and self interstitials . J Nucl Mater , 382 : 154 – 159 . doi: 10.1016/j.jnucmat.2008.08.019
  • Soneda , N , Ishino , S , Takahashi , A and Dohi , H . 2003 . Modeling the microstructural evolution in bcc-Fe during irradiation using kinetic Monte Carlo computer simulation . J Nucl Mater , 323 : 169 – 180 . doi: 10.1016/j.jnucmat.2003.08.021
  • Abe , H and Kuramoto , E . 1999 . Interaction of solutes with irradiation-induced defects of electron-irradiated dilute iron alloys . J Nucl Mater , 271&272 : 209 – 213 . doi: 10.1016/S0022-3115(98)00741-7
  • Murakami , K . 2011 . Study on irradiation defect behavior and aging degradation in reactor pressure vessel steels , Tokyo , , Japan : The University of Tokyo . PhD. theses
  • Watanabe , H , Masaki , S , Masubuchi , S , Yoshida , N and Dohi , K . 2012 . Effects of Mn addition on dislocation loop formation in A533B and model alloys . J Nucl Mater. , Available from: http://dx.doi.org/10.1016/j.jnucmat.2012.08.029
  • Fujii , K and Fukuya , K . 2005 . Characterization of defect clusters in ion-irradiated A533B steel . J Nucl Mater , 366 : 323 – 330 . doi: 10.1016/j.jnucmat.2004.10.090
  • Kasada , R , Kudo , T , Kimura , A , Matsui , H and Narui , M . 2005 . Effects of neutron dose, dose rate and irradiation temperature on the irradiation embrittlement of a low-copper reactor pressure vessel steel . J ASTM Int , 2 : JAI12399 doi: 10.1520/JAI12399
  • Tomimatsu , M , Sakamoto , H , Dohi , K , Watanabe , T and Matsuzawa , H . 2009 . “ Microstructural characterization of RPV steels irradiated to high fluences ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference PVP2009 , ASME . PVP2009-78103
  • Kuleshova , E A , Gurovich , B A , Shtrombakh , Ya I. , Nikolaev , Yu A. and Pechenkin , V A . 2005 . Microstructural behavior of VVER-440 reactor pressure vessel steels under irradiation to neutron fluences beyond the design operation period . J Nucl Mater , 342 : 77 – 89 . doi: 10.1016/j.jnucmat.2005.03.011
  • Fujii , K , Ohkubo , T and Fukuya , K . 2011 . Effects of solute elements on irradiation hardening and microstructural evolution in low alloy steels . J Nucl Mater , 417 : 949 – 952 . doi: 10.1016/j.jnucmat.2010.12.192
  • Hernandez-Mayoral , M and Gomea-Briceno , D . 2010 . Transmission electron microscopy study on neutron irradiated pure iron and RPV model alloys . J Nucl Mater , 399 : 146 – 153 . doi: 10.1016/j.jnucmat.2009.11.013
  • Lambrecht , M , Meslin , E , Malerba , L , Hernandez-Mayoral , M , Bergner , F , Pareige , P , Radiguet , B and Almazouzi , A . 2010 . On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels . J Nucl Mater , 406 : 84 – 89 . doi: 10.1016/j.jnucmat.2010.05.020
  • Nagai , Y , Takadate , K , Tang , Z , Ohkubo , H and Hasegawa , M . 2004 . “ Irradiation induced vacancy-Cu aggregations in Fe-Cu model alloys of reactor pressure vessel steels studied by positron annihilation ” . In Effects of Radiation on Materials: 21th International Symposium, ASTM STP 1447 , 590 – 604 . ASTM .
  • Lambrecht , M and Almazouzi , A . 2009 . Positron annihilation study of neutron irradiated model alloys and of a reactor pressure vessel steel . J Nucl Mater , 385 : 334 – 338 . doi: 10.1016/j.jnucmat.2008.12.020
  • Valo , M , Krause , R , Saarinen , K , Hautojarvi , P and Hawthorne , J R . 1992 . “ Irradiation response and annealing behavior of pressure vessel model steels and iron ternary alloys measured with positron techniques ” . In Effects of Radiation on Materials: 15th International Symposium, ASTM STP 1125 , 172 – 185 . ASTM .
  • Dohi , K , Soneda , N , Nomoto , A and Ishino , S . 2007 . Nano-structural changes in the RPV steels irradiated in MTR to high doses -3D atom probe and positron annihilation study . Report No.Q04025; CRIEPI , [in Japanese]
  • Nagai , Y , Takadate , K , Ohkubo , H , Hasegawa , M , tang , Z , Sunaga , H and Takizawa , H . 2003 . Positron annihilation study of vacancy-solute complex evolution in Fe-based alloys . Phys Rev B , 67 : 224202.1 doi: 10.1103/PhysRevB.67.224202
  • Carter , R G , Onchi , T , Soneda , N , Dohi , K , Hyde , J M , English , C A , Hutchings , M T , Server , W , Coste , J F and Van-Duysen , J C . 1998 . “ Thermal stability of matrix defects in irradiated pressure vessel steels ” . In Proceedings of the International Symposium Fontevraud IV, Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water reactors , FNES .
  • Soneda , N , Carter , R , Dohi , K , Ortner , S and Ishino , S . 2004 . “ Vacancy-type defects produced in reactor pressure vessel materials during neutron irradiation ” . In Presented in Fall annual Meeting of At. Energy Soc. Japan G49. [in Japanese]
  • Druce , S G , Gage , G and Jordan , G . 1986 . Effect of ageing on properties of pressure vessel steels . Acta Metal , 34 : 641 – 652 . doi: 10.1016/0001-6160(86)90179-3
  • Bischler , P JE and Wild , R K . 1996 . “ A microstructural study of phosphorus segregation and intergranular fracture in neutron irradiated submerged-arc weld ” . In Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270 , 260 – 273 . ASTM .
  • Lu , Z , Faulkner , R G , Jones , R B and Flewitt , P EJ . 2005 . Radiation- and thermally- induced phosphorus inter-granular segregation in pressure vessel steels . J ASTM Int , 2 : JAI12387 doi: 10.1520/JAI12387
  • Nakata , H , Fujii , K , Fukuya , K , Kasada , R and Kimura , A . 2006 . Grain boundary phosphorus segregation under thermal aging in low alloy steels . J Nucl Sci Technol , 43 : 785 – 793 . doi: 10.1080/18811248.2006.9711160
  • McElroy , R J , English , C A , Foreman , A J , Gage , G , Hyde , J M , Ray , P HN and Vatter , I A . 1999 . “ Temper embrittlement, irradiation induced phosphorus segregation and implications for post-irradiation annealing of reactor pressure vessels ” . In Effects of Radiation on Materials: 18th International Symposium, ASTM STP1325 , 296 – 316 . ASTM .
  • Gurovich , B A , Kuleshova , E A , Shtorombakh , Ya I and Zabusov , O O . 2000 . Intergranular and intragranular phosphorus segregation in Russian pressure vessel steels due to neutron irradiation . J Nucl Mater , 279 : 259 – 272 . doi: 10.1016/S0022-3115(00)00007-6
  • Kimura , A , Shibata , M , Kasada , R , Fujii , K , Fukuya , K and Nakata , H . 2005 . Assessment of neutron irradiation-induced grain boundary embrittlement by phosphorus segregation in a reactor pressure vessel steel . J ASTM Int , 2 : JAI12398
  • Nishiyama , Y , Onizawa , K and Suzuki , M . 2007 . Phosphorus segregation and intergranular embrittlement in thermally aged and neutron irradiated reactor pressure vessel steels . J ASTM Int , 4 : JAI100690 doi: 10.1520/JAI100690
  • Nishiyama , Y , Onizawa , K , Suzuki , M , Anderegg , J W , Nagai , Y , Toyama , T , Hasegawa , M and Kameda , J . 2008 . Effects of neutron-irradiation-induced intergranular phosphorus segregation and hardening on embrittlement in reactor pressure vessel steels . Acta Mater , 56 : 4510 – 4521 . doi: 10.1016/j.actamat.2008.05.026
  • Nishiyama , Y , Yamagushi , M , Onizawa , K , Iwase , A and Matsuzawa , H . 2009 . Irradiation-induced grain-boundary solute segregation and its effect on ductile-to-brittle transition temperature in reactor pressure vessel steels . J ASTM Int , 6 : JAI101959 doi: 10.1520/JAI101959
  • Jones , R B , Cowan , J R , Corcoran , R C and Walmsley , J C . 2000 . “ Embrittlement, hardening and grain boundary composition in an Fe-P-C alloy after irradiation or thermal aging ” . In Effects of Radiation on Materials: 19th International Symposium, ASTM STP1366 , 473 – 491 . ASTM .
  • Kameda , J and Bevolo , A J . 1989 . Neutron irradiation-induced intergranular solute segregation in iron base alloys . Acta Metall , 37 : 3283 – 3296 . doi: 10.1016/0001-6160(89)90201-0
  • Nikolaeva , A V , Nikolaev , Y A and Krykov , A M . 1994 . The contribution of grain boundary effects to low-alloy steel irradiation embrittlement . J Nucl Mater , 218 : 85 – 93 . doi: 10.1016/0022-3115(94)00361-0
  • Faulkner , R G , Song , S , Flewitt , P EJ , Victoria , M and Marmy , P . 1998 . Grain boundary segregation under neutron irradiation in dilute alloys . J Nucl Mater , 255 : 189 – 209 . doi: 10.1016/S0022-3115(98)00022-1
  • Ebihara , K , Yamagushi , M , Nishiyama , Y , Onizawa , K and Matsuzawa , H . 2009 . “ Numerical simulation of irradiation-induced grain-boundary phosphorus segregation in reactor pressure vessel steels using rate theory model with first-principles calculations ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2009 , ASME . PVP2009–77624
  • JEAC 4201-2007 . 2007 . Method of surveillance tests for structural materials of nuclear reactors . JEAC 4201-2007; JEAC ,
  • Soneda , N and Nomoto , A . 2009 . “ Characteristics of the new embrittlement correlation method for the Japanese reactor pressure vessel steels ” . In Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17 , ASME . ICONE17-75320
  • Eason , E D , Wright , J E and Odette , G R . 1998 . Improved embrittlement correlations for reactor pressure vessel steels . NUREG/CR-6551 ,
  • 2002 . “ Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF) ” . In Annual book of ASTM standards , Vol. 12.02 , Philadelphia : ASTM . ASTM E900-02
  • Eason , E D , Odette , G R , Nanstad , R K and Yamamoto , T . 2006 . “ A physically based correlation of irradiation-induced transition temperature shifts for RPV steels ” . In ORNL/TM-2006/530 , ORNL .
  • NRC-2007-0008 . 2010 . Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events . published in Federal Register , 75 No. 1, January 4
  • Bogaert , A- S. , Gerard , R and Chaouadi , R . 2010 . “ Comparison of embrittlement trend curves to high fluence surveillance results ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A137. [CD-ROM]
  • Todeschini , P , Lefebvre , Y , Churier-Bossennec , H , Rupa , N , Chas , G and Benhamou , C . 2010 . “ Revision of the irradiation embrittlement correlation used for the EDF RPV fleet ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A084. [CD-ROM]
  • May , J , Hein , H , Ganswinf , J and Wildera , M . 2010 . “ Irradiation behavior of German PWR RPV steels under operating conditions ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A055. [CD-ROM]
  • Nikolaev , Y uA . 2007 . Radiation embrittlement of Cr-Ni-Mo and Cr-Mo RPV steels . J ASTM Int , 4 : JAI100695 doi: 10.1520/JAI100695
  • Kirk , M T . 2010 . “ A wide-range trend embrittlement trend curve for western RPV steels ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A106. [CD-ROM]
  • Nanstad , R K and Odette , G R . 2009 . “ Reactor pressure vessel issues for the light-water reactor sustainability program ” . In Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor , 1667 – 1676 . ANS . [CD-ROM]
  • English , C A , Server , W L and Rosinski , S T . 2004 . Critical review of through-wall attenuation of mechanical properties in RPV steels . J ASTM Int , 1 : JAI11246 doi: 10.1520/JAI11246
  • Stoller , R E and Greenwood , L R . 2001 . “ An evaluation of through-thickness changes in primary damage production in commercial reactor pressure vessels ” . In Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405 , 204 – 217 . ASTM .
  • Brillaud , C , Grandjean , Y and Saittet , S . 2001 . “ Vessel investigation program of “CHOOZ A” PWR reactor after shutdown ” . In Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405 , 28 – 41 . ASTM .
  • Viehrig , H- W. , Schuhknecht , J , Rindelhardt , U and Weiss , F- P. 2009 . Investigation of beltline welding seam of the Geifswald WWER-440 unit 1 reactor pressure vessel . J ASTM Int , 6 : JAI101925 doi: 10.1520/JAI101925
  • Brumovsky , M , Kytka , M , Server , W , Soneda , N and Spanner , J . 2008 . “ Results on attenuation of neutron embrittlement effects ” . In Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 , ASME . ICONE16-48710
  • Server , W , Spanner , J , Rosinski , S , Brumovsky , M and Kytka , M . 2008 . Attenuation of neutron radiation damage through a simulated RPV wall . J ASTM Int , 5 : JAI100728 doi: 10.1520/JAI100728
  • Server , W , Brumovsly , M , Lytka , M , Soneda , N and Spanner , J . 2010 . Further results on attenuation of neutron embrittlement effects in a simulated RPV wall . J ASTM Int , 7 : JAI102070 doi: 10.1520/JAI102070
  • Sokolov , M A , Nanstad , R K and Miller , M K . 2004 . Fracture toughness and atom probe characterization of a highly embrittled RPV weld . J ASTM Int , 1 : JAI11312 doi: 10.1520/JAI11312
  • Onizawa , K and Suzuki , M . 2001 . “ Comparison of transition temperature shifts between static fracture toughness and Charpy-V impact properties due to irradiation and post-irradiation annealing for Japanese A533B-1 steels ” . In Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405 , 79 – 96 . ASTM .
  • Sokolov , M A and Nanstad , R K . 1999 . “ Comparison of irradiation-induced shifts of KJc and Charpy impact toughness for reactor pressure vessel steels ” . In Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325 , 167 – 190 . ASTM .
  • Wallin , K RW , Nagel , G , Keim , E and Siegele , D . 2005 . “ Estimation of master curve based RTTO reference temperature from CVN data ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2005 , ASME . PVP2005-71135
  • Lucon , E , Scibetta , M and Gerard , R . 2009 . Analysis of the Belgian surveillance Wfracture toughness database using conventional and advanced master curve approaches . J ASTM Int , 6 : JAI101897 doi: 10.1520/JAI101897
  • Chas , G , Parrot , A , Saillet , S , Bourgon , J , Rupa , N and Churier-Bossennec , H . 2002 . “ Irradiation effect on fracture toughness of core shell on PWR vessels ” . In Proceedings of the Int. Symposium on Fontevraud 5, Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors , 261 – 272 . SFEN .
  • Hein , H , Keim , E , Schnabel , H , Seibert , T and Gundermann , A . 2009 . Final results from the crack initiation and arrest of irradiated steel materials project on fracture mechanical assessments of pre-irradiated RPV steels used in German PWR . J ASTM Int , 6 : JAI101962 doi: 10.1520/JAI101962
  • Zurbuchen , C , Viehrig , H-W and Weiss , F-P . 2009 . Master curve and unified curve applicability to highly neutron irradiated western type reactor pressure vessel steels . Nucl Eng Design , 239 : 1246 – 1253 . doi: 10.1016/j.nucengdes.2009.03.008
  • Nanstad , R K , Sokolov , M A and McCabe , D E . 2008 . Applicability of the fracture toughness master curve to irradiated highly embrittled steel and intergranular fracture . J ASTM Int , 5 : JAI101346
  • Nanstad , R K , Brumovsky , M , Callejas , R H , Gillemot , F , Korshunov , M , Lee , B S , Lucon , E , Scibetta , M , Minnebo , P , Nilsson , K F , Miura , N , Onizawa , K , Planman , T , Server , W , Burgos , B and Serrano , M . 2009 . “ IAEA coordinated research project on master curve approach to monitor fracture toughness of RPV steels: final results of the experimental exercise to support constraint effects ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2009 , ASME . PVP2009-78022
  • Viehrig , H-W , Lucon , E and Server , W L . 2009 . “ IAEA coordinated research project on master curve approach to monitor fracture toughness of RPV steels: effect of loading rate ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2009 , ASME . PVP2009-77668
  • Scibetta , M , Lucon , E , Chaouadi , R , van Wall , E and Gerard , R . 2005 . Use of broken charpy V-notch specimens from a surveillance program for fracture toughness determination . J ASTM Int , 2 : JAI12450
  • Lucon , E and Scibetta , M . 2008 . Miniature compact tension specimens for upper shelf fracture toughness measurements on RPV steels . J ASTM Int , 5 : JAI100959
  • Miura , N and Soneda , N . 2010 . “ Evaluation of fracture toughness by master curve approach using miniature C(T) specimens ” . In Proceedings of the ASME 2010 Pressure Vessels and Piping Division / K-PVP Conference, PVP2010 , ASME . PVP2010- 25862
  • Schindler , H- J. , Tipping , P and Kalkhof , D . 2006 . “ Application of modern fracture mechanics methods to assess material degradation of NPP components ” . In Proceedings of the International Symposium on Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 855 – 864 . SFEN . A046
  • EricksonKirk , K T , EricksonKirk , M A , Roe , C and Zhang , X J . 2009 . “ Use of large database to identify trends in the behavior of ferritic steels ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2009 , ASME . PVP2009-77788
  • EricksonKirk , M . 2010 . “ Development of a Charpy master curved-based embrittlement trend curve ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A105. [CD-ROM]
  • Naudin , C , Frunf , J-M and Pineau , A . 2001 . “ Toughness modeling of PWR vessel steel containing segregated zones ” . In Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , NACE . [CD-ROM]
  • Saillet , S , Rupa , N and Benhamou , C . 2006 . “ Impact of large forging macrosegregations on the reactor pressure vessel surveillance program ” . In Proceedings of the International Symposium on Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 731 – 744 . SFEN . A067
  • Lucon , E , Leenaers , A , Vandermeulen , W and Scibetta , M . 2010 . Investigation of transition fracture toughness variation within the thickness of reactor pressure vessel forging . J ASTM Int , 7 : JAI102431
  • Viehrig , H- W. , Schuhknecht , J , Rindelhardt , U and Weiss , F-P . 2009 . Investigation of beltline welding seam of the Greifswald WWER-440 unit 1 reactor pressure vessel . J ASTM Int , 6 : JAI101925 doi: 10.1520/JAI101925
  • Moinereau , D and Bezdikian , G . 2005 . “ SMILE: A European R&D program for the inclusion of warm pre-stress in RPV assessment ” . In Trans. 18th International Conference on Structural Mechanics in Reactor Technology, SMiRT18 Paper 18-G07-1
  • Moinereau , D , Dahl , A , Chapuliot , S and Lidbury , D . 2006 . “ SMILE project The effect of warm pre-stress in RPV assessment: synthesis of experimental results and analyses ” . In Proceedings of the 2006 ASME Pressure Vessels and Piping Division Conference, PVP2006-ICPVT-11 , ASME . PVP2006-93178
  • Keim , E , Langer , R , Schnabel , H and Bartsch , R . 2005 . “ Warm pre-stress effect measured at irradiated RPV weld material ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2005 , ASME . PVP2005-71196
  • Moinereau , D , Dahl , A , Chas , G , Rupa , N , Bourgoin , J and Churier-Bossennec , H . 2006 . “ Application of warm pre-stress to RPV assessment ” . In Proceedings of the International Symposium on Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 817 – 828 . SFEN . A002
  • Massoud , J- P. , Bugat , S , Marini , B , Lidbury , D and Van Dyck , S . 2010 . PERFECT - Prediction of Irradiation Damage Effects on Reactor Components: A summary . J Nucl Mater , 406 : 2 – 6 . doi: 10.1016/j.jnucmat.2010.09.029
  • Lidbury , D , Keim , E , Marini , B , Malerba , L and Zeghadi , A . 2010 . “ Overview of RPV sub-project of PERFORM 60 ” . In Proceedings of the International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A143. [CD-ROM]
  • Al-Mazouzi , A , Alamo , A , Lidbury , D , Moinereau , D and Van Dyck , S . 2011 . PERFORM60: prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling – 60 years foreseen . Nucl Eng Design , 241 : 3403 – 3415 . doi: 10.1016/j.nucengdes.2011.01.054
  • FP6 IP PERFECT project . 2010 . prediction of irradiation damage effects in reactor components . J Nucl Mater , 406 : 1 – 204 . doi: 10.1016/j.jnucmat.2009.04.006
  • Vincent , E , Domain , C and Becquart , C S . 2005 . Ab initio calculations of vacancy interactions with solute atoms in bcc Fe . Nucl Instrum Methods , B228 : 137 – 141 .
  • Jumel , S , Van Duysen , J-C , Ruste , J and Domain , C . 2005 . Interactions between dislocations and irradiation-induced defects in light water reactor pressure vessel steels . J Nucl Mater , 346 : 79 – 97 . doi: 10.1016/j.jnucmat.2005.04.065
  • Mathieu , J- P. , Inal , K , Berveiller , S and Diard , O . 2009 . A micromechanical interpretation of the temperature dependence of Beremin model parameters for French RPV steel . J Nucl Mater , 406 : 97 – 112 . doi: 10.1016/j.jnucmat.2010.02.025
  • Mathieu , J- P. , Diard , O , Inal , K and Berveiller , S . 2008 . “ Micromechanical modeling of brittle fracture of French RPV steel. A comprehensive study of stress triaxiality effect ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2008 , ASME . PVP2008-61334
  • Zhao , X , Quita da Fonseca , J , Sherry , A and Lidbury , D . 2008 . “ Grain-scale heterogeneity on mechanistic modeling of cleavage fracture of a ferritic RPV steel forging material ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2008 , ASME . PVP2008-61569
  • Margolin , B , Shvetsova , V , Gulenko , A , Nikolaev , V , Lidbury , D and Keim , E . 2008 . “ Physical and mechanical aspects of radiation embrittlement of RPV steels ” . In Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP2008 , ASME . PVP2008-61133
  • Bouchet , C , Tanguy , B , Besson , J and Bugat , S . 2005 . Prediction of the effects of neutron irradiation on the Charpy ductile to brittle transition curve of an A508 pressure vessel steel . Comp Mater Sci , 32 : 294 – 300 . doi: 10.1016/j.commatsci.2004.09.039
  • Kodama , M , Katsura , R , Morisawa , J , Nishimura , S , Suzuki , S , Asano , K , Fukuya , K and Nakata , K . 1993 . “ IASCC susceptibility of austenitic stainless steels irradiated to high fluence ” . In Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 583 – 588 . TMS .
  • Suzuki , I , Kanasaki , H , Mimaki , H , Akiyama , M , Okubo , T , Mishima , Y and Mager , T R . 1996 . “ Stress corrosion cracking of irradiated stainless steels in simulated PWR primary water ” . In Proceedings of the 5th International Conference on Nuclear Engineering, ICONE-5 205
  • Fukuya , K , Nakano , M , Fujii , K and Torimaru , T . 2004 . IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels . J Nucl Sci Technol , 41 : 673 – 681 . doi: 10.1080/18811248.2004.9715532
  • Fukuya , K , Nishioka , H , Fujii , K and Torimaru , T . 2008 . Effects of dissolved hydrogen and strain rate on IASCC behavior in highly irradiated stainless steels . J Nucl Sci Technol , 45 : 452 – 458 . doi: 10.1080/18811248.2008.9711454
  • Chung , H M , Ruther , W E , Sanecki , J E , Hins , A , Zalzec , N J and Kassner , T F . 1996 . Irradiation-assisted stress corrosion cracking of austenitic stainless steels: recent progress and new approaches . J Nucl Mater , 239 : 61 – 79 . doi: 10.1016/S0022-3115(96)00677-0
  • Tanaka , Y , Suzuki , S , Kodama , M , Nishimura , S , Fukuya , K , Sakamoto , H , Nakata , K and Kato , T . 1995 . “ IASCC susceptibility of type 304, 304L and 316L stainless steels ” . In Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 803 – 811 . ANS .
  • Kasahara , S , Nakata , K , Jacobs , A J , Wozadlo , G P , Fukuya , K , Shima , S and Suzuki , S . 1993 . “ The effects of minor elements on IASCC susceptibility in austenitic stainless steels irradiated with neutrons ” . In Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 615 – 621 . TMS .
  • Fournier , L , Sencer , B H , Was , G S , Simonen , E P and Bruemmer , S M . 2003 . The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels . J Nucl Mater , 321 : 192 – 209 . doi: 10.1016/S0022-3115(03)00243-5
  • Nakano , J , Miwa , Y , Kohya , T and Tsukada , T . 2004 . Effects of silicon, carbon and molybdenum additions on IASCC of neutron irradiated austenitic stainless steels . J Nucl Mater , 329–333 : 643 – 647 . doi: 10.1016/j.jnucmat.2004.04.098
  • Katsura , R , Morisawa , J , Kodama , M , Nishimura , S , Suzuki , S , Shima , S and Yamamoto , M . 1993 . “ Effect of stress on IASCC in irradiated austenitic stainless steels ” . In Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 625 – 631 . TMS .
  • Jacobs , A J , Wozadlo , G P and Gordon , G M . 1993 . Use of a constant deflection test to evaluate susceptibility to irradiation-assisted stress corrosion cracking . Corrosion , 49 : 650 – 655 . doi: 10.5006/1.3316096
  • Nishioka , H , Fukuya , K , Fujii , K and Torimaru , T . 2008 . IASCC initiation in highly irradiated stainless steels under uniaxial constant load conditions . J Nucl Sci Technol , 45 : 1072 – 1077 . doi: 10.1080/18811248.2008.9711894
  • Conermann , J , Shogan , R , Fujimoto , K , Yonezawa , T and Tamaguchi , Y . 2005 . “ Irradiation effects in a highly irradiated cold worked stainless steel removed from a commercial PWR ” . In Proceedings of the 12th International Conference Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 277 – 284 . TMS . [CD-ROM]
  • Freyer , P , Mager , T and Burke , M . 2007 . “ Hot cell crack initiation testing of various heats of highly irradiated 316 stainless steel components obtained from three commercial PWRs ” . In Proceedings of the 13th International Conference Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Takakura , K , Nakata , K , Ando , M , Fujimoto , K and Wachi , E . 2007 . “ Lifetime evaluation for IASCC initiation of cold worked 316 stainless steel's BFB in PWR primary water ” . In Proceedings of the13th International Conference Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Toivonen , A , Aaltonen , P , Karlsen , W , Ehrnsten , U , Massoud , J and Boursier , J . 2006 . “ Post- irradiation SCC investigations on highly-irradiated core internals component materials ” . In Proceedings of the 6th International Symposium Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 567 – 580 . SFEN . A099
  • Fujii , K , Nishioka , H , Fukuya , K and Torimaru , T . 2010 . “ Effects of dissolved hydrogen on IASCC behavior ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A085. [CD-ROM]
  • Pokor , C , Massoud , J-P , wintergerst , M , Toivonen , A , Egrnsten , U and Karlsen , W . 2010 . “ Determination of the time to failure curves as a function of stress for a highly irradiated AISI 304 stainless steel after constant load tests in simulated PWR water environment ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A008. [CD-ROM]
  • Takakura , K , Tanaka , S , Nakamura , T , Chatani , K and Kaji , Y . 2010 . “ IASCC evaluation method for irradiated core internal structures in BWR power plants ” . In Proceedings of the ASME 2010 Pressure Vessels & Piping Division/ K-PVP Conference, PVP2010 , ASME . PVP2010-25293
  • Ooki , S , Tanaka , Y , Takamori , K , Suzuki , S , Tanaka , S , Ishiyama , Y , Nakamura , T , Kato , T , Chatani , K and Kodama , M . 2005 . “ Study on SCC growth behavior of BWR core shroud ” . In Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 365 – 378 . TMS . [CD-ROM]
  • Karlsen , T M , Bennett , P and Hogberg , N W . 2005 . “ In-core crack growth rate studies on irradiated austenitic stainless steels in BWR and PWR conditions in the Halden reactor ” . In Proceedings of the 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 337 – 348 . TMS . [CD-ROM]
  • Chen , Y , Alexandreanu , B , Yang , Y , Shack , W J , Natesan , K , Gruber , E E and Rao , A S . 2011 . “ Crack growth behavior of irradiated type 316 SS in low dissolved oxygen environment ” . In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1169 – 1182 . TMS . [CD-ROM]
  • Karlsen , T M and Horvath , A . 2004 . Final report on the in-pile crack growth behaviour of irradiated compact tension specimens in IFA-639 . OECD Halden Reactor Project Report HWR-770, Dec. ,
  • Jenssen , A , Stjärnsäter , J and Pathania , R . 2011 . “ Crack growth rates of irradiated commercial stainless steels in BWR and PWR environments ” . In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1229 – 1240 . TMS . [CD-ROM]
  • Jenssen , A , Stjärnsäter , J and Pathania , R . 2009 . “ Crack growth rate testing of fast reactor irradiated type 304L and 316 SS in BWR and PWR environments ” . In Proceedings of the 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1164 – 1180 . ANS . [CD-ROM]
  • Andresen , P L and Ford , F P . 1988 . Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems . Mater Sci Eng , A103 : 167 – 184 .
  • Kaji , Y , Ugachi , H , Tsukada , T , Nakano , J , Matsui , Y , Kawamata , K , Shibata , A , Ohmi , M , Nagata , N , Dozaki , K and Takiguchi , H . 2008 . In-core SCC growth behavior of type 304 stainless steel in BWR simulated high-temperature water at JMTR . J Nucl Sci Technol , 45 : 725 – 734 . doi: 10.1080/18811248.2008.9711473
  • Fukuya , K , Nakata , K and Horie , A . 1991 . “ An IASCC study using high energy ion irradiation ” . In Proceedings of the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 814 – 820 . ANS .
  • Was , G S , Busby , J T , Allen , T , Kenik , E A , Jensson , A , Bruemmer , S M , Gan , J , Edwards , A D , Scott , P M and Andresen , P L . 2002 . Emulation of neutron irradiation effects with protons: validation of principle . J Nucl Mater , 300 : 198 – 216 . doi: 10.1016/S0022-3115(01)00751-6
  • Tsukada , T , Jitsukawa , S , Shiba , K , Sato , Y , Shibahara , I and Nakajima , H . 1993 . Evaluation of irradiation assisted stress corrosion cracking (IASCC) of type 316 stainless steel irradiated in FBR . J Nucl Mater , 207 : 159 – 168 . doi: 10.1016/0022-3115(93)90258-Z
  • Chung , H M , Strain , R V and Shack , W J . 2001 . Tensile and stress corrosion cracking properties of type 304 stainless steel irradiated to a very high dose . Nucl Eng Design , 208 : 221 – 234 . doi: 10.1016/S0029-5493(01)00411-3
  • Fujimoto , K , Yonezawa , T , Wachi , E , Yamaguchi , Y , Nakano , M , Shogan , R P , Massoud , J P and Mager , T R . 2005 . “ Effect of the accelerated irradiation and hydrogen/helium gas on IASCC characteristics for highly irradiated austenitic stainless steels ” . In Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 299 – 310 . TMS . [CD-ROM]
  • Zinkle , S J , Maziasz , P J and Stoller , R E . 1993 . Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steels . J Nucl Mater , 206 : 266 – 286 . doi: 10.1016/0022-3115(93)90128-L
  • Garner , F A . 1993 . Evolution of microstructure in face-centered cubic metals during irradiation . J Nucl Mater , 205 : 98 – 117 . doi: 10.1016/0022-3115(93)90076-B
  • Maziasz , P J . 1989 . Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels . J Nucl Mater , 169 : 95 – 115 . doi: 10.1016/0022-3115(89)90525-4
  • Edwards , D J , Simonen , E P and Brummer , S M . 2003 . Evolution of fine-scale defects in stainless steels neutron-irradiated at 275°C . J Nucl Mater , 317 : 13 – 31 . doi: 10.1016/S0022-3115(03)00002-3
  • Edwards , D J , Simonen , E P , Garner , F A , Greenwood , L R , Oliver , B M and Bruemmer , S M . 2003 . Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS . J Nucl Mater , 317 : 32 – 45 . doi: 10.1016/S0022-3115(03)00003-5
  • Edwards , D J , Garner , F A , Bruemmer , S M and Efsing , P . 2009 . Nano-cavities observed in a 316SS flux thimble tube irradiated to 33 and 70 dpa . J Nucl Mater , 384 : 249 – 255 . doi: 10.1016/j.jnucmat.2008.11.025
  • Fukuya , K , Fujii , K , Nishioka , M and Kitsunai , Y . 2006 . Evolution of microstructure and microchemistry in cold-worked 316 stainless steels under PWR irradiation . J Nucl Sci Technol , 43 : 159 – 173 . doi: 10.1080/18811248.2006.9711078
  • Bailat , C , Almazouzi , A , Baluc , N , Schaublin , R , Groschel , F and Victoria , M . 2000 . The effects of irradiation and testing temperature on tensile behavior of stainless steels . J Nucl Mater , 283–287 : 446 – 450 . doi: 10.1016/S0022-3115(00)00083-0
  • Monnet , I , Decroix , G M , Dubuisson , P , Reuchet , J and Morlent , O . 2002 . “ Investigation of the Chooz A nuclear power plant ” . In Proceedings of the International Symposium Fontevraud 5, Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors , 371 – 379 . SFEN .
  • Demma , A , Carter , R , Jenssen , A , Torimaru , T and Gamble , R . 2007 . “ Fracture toughness of highly irradiated stainless steels in boiling water reactors ” . In Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Torimaru , T , Kodama , M , Tanaka , S , Nakamura , T , Asano , K and Kumagai , K . 2005 . Neutron flux effect on the irradiation hardening of type 304 stainless steel . J ASTM Int , 2 : JAI12843 doi: 10.1520/JAI12843
  • Pokor , C , Brechet , Y , Dubuisson , P , Massoud , J P and Barbu , A . 2004 . Irradiation damage in 304 and 316 stainless steels: Experimental investigation and modeling, Part I: Evolution of the microstructure . J Nucl Mater , 326 : 19 – 29 . doi: 10.1016/j.jnucmat.2003.11.007
  • Yang , Y , Allen , T R , Chen , Y and Chopra , O K . 2007 . “ Microstructural evaluation of stainless alloys irradiated in the BOR-60 reactor ” . In Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Gan , J , Was , G S and Stoller , R E . 2001 . Modeling of microstructural evolution in austenitic stainless steels irradiated under light water reactor condition . J Nucl Mater , 299 : 53 – 67 . doi: 10.1016/S0022-3115(01)00673-0
  • Etienne , A , Radiguet , B , Pareige , P , Massoud , J-P and Pokor , C . 2008 . Tomographic atom probe characterization of the microstructure of a cold worked 316 stainless steel after neutron irradiation . J Nucl Mater , 382 : 64 – 69 . doi: 10.1016/j.jnucmat.2008.09.015
  • Pareige , P , Etienne , A and Radiguet , B . 2009 . Experimental atomic scale investigation of radiation effects in CW 316SS and UFG-CW 316SS . J. Nucl. Mater , 389 : 259 – 264 . doi: 10.1016/j.jnucmat.2009.02.009
  • Etienne , A , Radiguet , B , Cunningham , N J , Odette , G R and Pareige , P . 2010 . Atomic scale investigation of radiation-induced segregation in austenitic stainless steels . J Nucl Mater , 406 : 244 – 250 . doi: 10.1016/j.jnucmat.2010.08.043
  • Jiao , Z and Was , G S . 2011 . Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels . Acta Mater , 59 : 1220 – 1238 . doi: 10.1016/j.actamat.2010.10.055
  • Toyama , T , Nozawa , Y , Van Renterghem , W , Matsukawa , Y , Hatakeyama , M. , Nagai , Y. , Al Mazouzi , A and Van Dyck , S . 2011 . Irradiation-induced precipitates in a neutron irradiated 304 stainless steel studied by three-dimensional atom probe . J Nucl Mater , 418 : 62 – 68 . doi: 10.1016/j.jnucmat.2011.07.027
  • Toyama , T , Nozawa , Y , Van Renterghem , W , Matsukawa , Y , Hatakeyama , M , Nagai , Y , Al Mazouzi , A and Van Dyck , S . 2012 . Grain boundary segregation in neutron-irradiated 304 stainless steel studied by atom probe tomography . J Nucl Mater , 425 : 71 – 75 . doi: 10.1016/j.jnucmat.2011.11.072
  • Hashimoto , N , Wakai , E and Robertson , J P . 1999 . Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR . J Nucl Mater , 273 : 95 – 101 . doi: 10.1016/S0022-3115(99)00009-4
  • Lucas , G E . 1993 . The evolution of mechanical property change in irradiated austenitic stainless steels . J Nucl Mater , 206 : 287 – 305 . doi: 10.1016/0022-3115(93)90129-M
  • Arai , H , Masanori , S , Mager , T R , Akiyama , M , Okubo , T and Mishima , Y . 1993 . “ Irradiation embrittlement of PWR reactor internals ” . In Proceedings of the ASME/JSME Nuclear Engineering Conference , Vol. 2 , 101 – 106 . ASME .
  • Suzuki , S , Saito , K , Kodama , M , Shima , S and Saito , T . 1991 . “ Evaluation of irradiation assisted degradation to BWR reactor internal components ” . In Trans. 11th International Conference on Structural Mechanics in Reactor Technology, SMiRT11 Vol. D , 321
  • Fukuya , K , Shima , S , Nakata , K , Kasahara , S , Jacobs , A J , Wozadlo , G P , Suzuki , S and Kitamura , M . 1993 . “ Mechanical properties and IASCC susceptibility in irradiated stainless steels ” . In Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 565 – 572 . TMS .
  • Kodama , M , Nishimura , S , Tanaka , Y , Suzuki , S , Fukuya , K , Shima , S , Nakata , K and Kato , T . 1995 . “ Mechanical properties of various kinds of irradiated austenitic stainless steels ” . In Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 831 – 838 . ANS .
  • Busby , J T , Hash , M C and Was , G S . 2005 . The relationship between hardness and yield stress in irradiated austenitic and ferritic steels . J Nucl Mater , 336 : 267 – 278 . doi: 10.1016/j.jnucmat.2004.09.024
  • Hashimoto , N , Zinkle , S J , Rowcliff , A F , Robertson , J P and Jitsukawa , S . 2000 . Deformation mechanisms in 316 stainless steel irradiated at 60°C and 330°C . J Nucl Mater , 283–287 : 528 – 534 . doi: 10.1016/S0022-3115(00)00087-8
  • Bailat , C , Groschel , F and Victoria , M . 2000 . Deformation modes of proton and neutron irradiated stainless steels . J Nucl Mater , 276 : 283 – 288 . doi: 10.1016/S0022-3115(99)00222-6
  • Byun , T S , Hashimoto , N and Farrell , K . 2006 . Deformation mode map of irradiated 316 stainless steel in true stress-dose space . J Nucl Mater , 351 : 303 – 315 . doi: 10.1016/j.jnucmat.2006.02.033
  • Byun , T S and Hashimoto , N . 2007 . Strain hardening during mechanical twinning and dislocation channeling in irradiated 316 stainless steels . J ASTM Int , 4 : JAI100680 doi: 10.1520/JAI100680
  • Nishioka , H , Fukuya , K , Fujii , K and Kitsunai , Y . 2008 . Deformation structure in highly irradiated stainless steels . J Nucl Sci Technol , 45 : 274 – 287 . doi: 10.1080/18811248.2008.9711437
  • Onchi , T , Dohi , K , Navas , M and Karlsen , W . 2006 . Crack initiation mechanism in non-ductile cracking of irradiated 304L stainless steels under BWR water environment . J Nucl Sci Technol , 43 : 851 – 865 . doi: 10.1080/18811248.2006.9711170
  • Jiao , Z and Was , G S . 2011 . Impact of localized deformation on IASCC in austenitic stainless steels . J Nucl Mater , 408 : 246 – 256 . doi: 10.1016/j.jnucmat.2010.10.087
  • Was , G S , Farkas , D and Robertson , I M . 2012 . Micromechanics of dislocation channeling in intergranular stress corrosion crack nucleation . Curr Opin Solid State Mater Sci , 16 : 134 – 142 . doi: 10.1016/j.cossms.2012.03.003
  • Karlsen , W , Pakarinen , J , Toivonen , A and Ehrnstén , U . 2011 . “ Deformation microstructures of 30 dpa AISI 304 stainless steel after monotonic tensile and constant load autoclave testing ” . In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1429 – 1444 . TMS . [CD-ROM]
  • Kamaya , M , Fukuya , K and Kitamura , T . 2009 . Angular distribution of slip steps by three-dimensional polycrystalline model for stainless steel . J Nucl Sci Technol , 46 : 901 – 906 . doi: 10.1080/18811248.2009.9711598
  • Hashimoto , N and Byun , T S . 2007 . Deformation-induced martensite formation and dislocation channeling in neutron-irradiated 316 stainless steel . J Nucl Mater , 367–370 : 960 – 965 . doi: 10.1016/j.jnucmat.2007.03.204
  • Cole , J I and Bruemmer , S M . 1993 . Post-irradiation deformation characteristics of heavy-ion irradiated 304LSS . J Nucl Mater , 225 : 53 – 58 . doi: 10.1016/0022-3115(94)00672-5
  • Jiao , Z and Was , G S . 2008 . Localized deformation and IASCC initiation in austenitic stainless steels . J Nucl Mater , 382 : 203 – 209 . doi: 10.1016/j.jnucmat.2008.08.032
  • Miura , T , Fujii , K , Fukuya , K and Ito , Y . 2009 . Characterization of deformation structure using ion-irradiated stainless steels . J Nucl Mater , 386–388 : 210 – 213 . doi: 10.1016/j.jnucmat.2008.12.093
  • Tanno , T , Hasegawa , A , Sasaki , S , Nogami , S and Satou , M . 2009 . “ Evaluation of localized deformation at low strain levels in austenitic stainless steel irradiated by proton ” . In Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1289 – 1293 . ANS . [CD-ROM]
  • Fukuya , K , Nishioka , H , Fujii , K , Miura , T and Torimaru , T . 2011 . An EBSD examination of SUS316 stainless steel irradiated to 73dpa and deformed at 593K . J Nucl Mater , 417 : 958 – 962 . doi: 10.1016/j.jnucmat.2010.12.301
  • Jiao , Z , Busby , J T , Obata , R and Was , G S . 2005 . “ Influence of localized deformation on irradiation-assisted stress corrosion cracking of proton-irradiated austenitic alloys ” . In Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 379 – 388 . TMS . [CD-ROM]
  • Williams , J F , Mager , T R , Spellward , P , Walmsley , J , Koyama , M , Suzuki , I and Mishima , H . 1997 . “ Microstructural effects in austenitic stainless steel materials irradiated in a pressurized water reactor ” . In Proceedings of the 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 725 – 733 . NACE .
  • Asano , K , Fukuya , K , Nakata , K and Kodama , M . 1991 . “ Changes in grain boundary composition induced by neutron irradiation on austenitic stainless steels ” . In Proceedings of the 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 838 – 843 . ANS .
  • Allen , T R , Cole , J I , Kenik , E A and Was , G S . 2008 . Analyzing the effect of displacement rate on radiation-induced segregation in 304 and 316 stainless steels by examining irradiated EBR-II components and samples irradiated with protons . J Nucl Mater , 376 : 169 – 173 . doi: 10.1016/j.jnucmat.2008.01.025
  • Simonen , E P , Edwards , D J and Bruemmer , S M . 2005 . “ Dose rate effects on microchemistry and microstructure relevant to LWR components ” . In Proceedings of the 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 429 – 438 . TMS . [CD-ROM]
  • Allen , T R , Busby , J T , Was , G S and Kenik , E A . 1998 . On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys . J Nucl Mater , 255 : 44 – 58 . doi: 10.1016/S0022-3115(98)00010-5
  • Kano , F , Fukuya , K , Hamada , S and Miwa , Y . 1998 . Effect of carbon and nitrogen on grain boundary segregation in irradiated stainless steels . J Nucl Mater , 258–263 : 1713 – 1717 . doi: 10.1016/S0022-3115(98)00289-X
  • Hackett , M J , Busby , J T , Miller , M K and Was , G S . 2009 . Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels . J Nucl Mater , 389 : 265 – 278 . doi: 10.1016/j.jnucmat.2009.02.010
  • Perks , J M and Murphy , S M . 1987 . “ Modelling the major element radiation-induced segregation in concentrated Fe-Cr-Ni alloys ” . In Proceedings of the of Materials for Nuclear Reactor Core Application , 165 – 169 . BNES .
  • Johnson , R A and Lam , N Q . 1976 . Solute segregation in metals under irradiation . Phys Rev B , 13 : 4346 – 4375 .
  • Allen , T R and Was , G S . 1998 . Modeling radiation-induced segregation in austenitic Fe-Cr-Ni alloys . Acta Mater , 46 : 3679 – 3691 . doi: 10.1016/S1359-6454(98)00019-6
  • Sakaguchi , N , Watanabe , S and Takahashi , H . 2001 . Heterogeneous dislocation formation and solute redistribution near grain boundaries in austenitic stainless steel under electron irradiation . Acta Mater , 49 : 1129 – 1137 . doi: 10.1016/S1359-6454(01)00031-3
  • Simonen , E P , Edwards , D J and Bruemmer , S M . 2005 . “ Dose rate ffects on microchemistry and microstructure relevant to LWR components ” . In Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 429 – 438 . TMS . [CD-ROM]
  • Sakaguchi , N , Takahashi , H and Ichinose , H . 2005 . Influence of silicon and phosphorus on radiation-induced segregation of chromium and nickel in austenitic model alloys . Mater Trans , 46 : 440 – 444 . doi: 10.2320/matertrans.46.440
  • Fukuya , K and Fujii , K . 2009 . A multicomponent model of radiation induced segregation in commercial stainless steels . J Nucl Sci Technol , 46 : 744 – 752 . doi: 10.1080/18811248.2007.9711581
  • Tucker , J D , Najafabadi , R , Allen , T R and Morgan , D . 2010 . Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys. . J Nucl Mater , 405 : 216 – 234 . doi: 10.1016/j.jnucmat.2010.08.003
  • Satoh , T , Satoh , Y and Uchida , S . 2003 . Water chemistry in a crack tip under irradiation, (II) Evaluation of oxidant concentration in the crack tip . J Nucl Sci Technol , 40 : 334 – 342 . doi: 10.1080/18811248.2003.9715363
  • Murayama , Y , Satoh , T , Uchida , S , Satoh , Y , Nagata , S , Satoh , T , Wada , Y and Tachibana , M . 2002 . Effects of hydrogen peroxide on intergranular stress corrosion cracking of stainless steel in high temperature water, (V) Characterization of oxide film on stainless steel by multilateral surface analyses . J Nucl Sci Technol , 39 : 1199 – 1206 . doi: 10.1080/18811248.2002.9715311
  • Miyazawa , T , Terachi , T , Uchida , S , Satoh , T , Tsukada , T , Satoh , Y , Wada , Y and Hosokawa , H . 2006 . Effects of hydrogen peroxide on corrosion of stainless steel, (V) Characterization of oxide film with multilateral surface analyses . J Nucl Sci Technol , 43 : 884 – 895 . doi: 10.1080/18811248.2006.9711173
  • Wada , Y , Ishida , K , Watanabe , A , Tachibana , M , Anzai , M and Fuse , M . 2009 . “ Effects of g-ray irradiation upon SCC initiation and propagation under BWR conditions ” . In Proceedings of the 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 596 – 603 . ANS . [CD-ROM]
  • Uchida , S , Satoh , T , Tsukada , T , Miyazawa , T , Satoh , Y and Ishii , K . 2009 . “ Evaluation of the effects of oxide film on electrochemical corrosion potential of stainless steel in high temperature water ” . In Proceedings of the 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1100 – 1121 . ANS . [CD-ROM]
  • Ehrlich , K . 1981 . Irradiation creep and interrelation with swelling in austenitic stainless steels . J Nucl Mater , 100 : 149 – 166 . doi: 10.1016/0022-3115(81)90531-6
  • Kenfield , T A , Busboom , H J and Appleby , W K . 1977 . In-reactor stress relaxation in bending of 20% cold-worked 316 stainless steel . J Nucl Mater , 65 : 238 – 243 . doi: 10.1016/0022-3115(77)90061-7
  • Causey , A R , Carpenter , G JC and MacEwen , S R . 1980 . In-reactor stress relaxation of selected metals and alloys at low temperatures . J Nucl Mater , 90 : 216 – 223 . doi: 10.1016/0022-3115(80)90258-5
  • Kaji , Y , Miwa , Y , Tsukada , T , Kikuchi , M , Kita , S , Yonekawa , M , Nakano , J , Tsuji , H and Nakajima , H . 2002 . Evaluation of in-pile and out-of-pile stress relaxation in 316L stainless steel under uniaxial loading . J Nucl Mater , 307–311 : 331 – 334 . doi: 10.1016/S0022-3115(02)01204-7
  • Ishiyama , Y , Nakata , K , Obata , M , Anzai , H , Tanaka , S , Tsukada , T and Asano , K . 2003 . “ Stress relaxation caused by neutron-irradiation at 561 K in austenitic stainless steels ” . In Proceedings of the 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 920 – 928 . ANS . [CD-ROM]
  • Obata , M , Root , J H , Ishiyama , Y , Nakata , K , Sakamoto , H , Anzai , H and Asano , K . 2006 . Radiation-induced stress relaxation of welded type 304 stainless steel evaluated by neutron diffraction . J ASTM Int , 3 : JAI12348 doi: 10.1520/JAI12348
  • Ishiyama , Y , Rogge , R B and Obata , M . 2011 . Radiation-induced stress relaxation in high temperature water of type 316L stainless steel evaluated by neutron diffraction . J Nucl Mater , 408 : 153 – 160 . doi: 10.1016/j.jnucmat.2010.11.023
  • Garnier , J , Dubuisson , P , Pokor , C , Lemaire , E , Monteil , N and Massoud , J-P . 2010 . “ Relaxation and irradiation creep of PWR baffle bolt materials ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A150. [CD-ROM]
  • Takakura , K , Sakima , K , Fujimoto , K , Kubo , N and Kido , T . 2010 . “ In-pile creep behavior of type 316 stainless steel at HALDEN reactor ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A132. [CD-ROM]
  • Foster , J P and Karlsen , T M . 2011 . “ Irradiation creep and irradiation stress relaxation of 316 and 304L stainless steels in thermal and fast neutron spectrum reactors ” . In Proceedings of the 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1339 – 1350 . TMS . [CD-ROM]
  • Foster , J P , Bunde , K and Gilbert , E R . 1998 . Stress state dependence of transient irradiation creep in 20% cold worked 316 stainless steel . J Nucl Mater , 257 : 118 – 125 . doi: 10.1016/S0022-3115(98)00447-4
  • Nakagawa , J , Ueno , K , Murase , Y and Yamamoto , N . 2007 . Effect of cold-work on the radiation-induced deformation of austenitic stainless steels . J Nucl Mater , 367–370 : 910 – 914 . doi: 10.1016/j.jnucmat.2007.03.063
  • Nagakawa , J . 1995 . Calculation of radiation-induced creep and stress relaxation . J Nucl Mater , 225 : 1 – 7 . doi: 10.1016/0022-3115(95)00015-1
  • Nagakawa , J and Ueno , K . 2004 . Calculation of radiation-induced deformation of SUS316 in the ITER-relevant condition . J Nucl Mater , 329–333 : 597 – 601 . doi: 10.1016/j.jnucmat.2004.04.106
  • Kodama , M , Ishiyama , Y , Namatame , S , Suzuki , S , Fukuya , K , Sakamoto , H , Nakata , K and Kato , T . 1999 . “ Effect of pre-irradiation grain boundary chemistry on IASCC ” . In Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 923 – 929 . TMS .
  • Chatani , K , Takakura , K , Ando , M , Nakata , K , Tanaka , S , Ishiyama , Y , Hishida , M and Kaji , Y . 2011 . “ IASCC crack growth rate of neutron irradiated low carbon austenitic stainless steels in simulated BWR condition ” . In Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Fukuya , K , Nakano , M , Fujii , K and Torimaru , T . 2004 . Separation of microstructural and microchemical effects in IASCC using post-irradiation annealing . J Nucl Sci Technol , 41 : 1218 – 1227 . doi: 10.1080/18811248.2004.9726351
  • Andresen , P L and Morra , M M . 2008 . IGSCC of non-sensitized stainless steels in high temperature water . J Nucl Mater , 383 : 97 – 111 . doi: 10.1016/j.jnucmat.2008.08.005
  • Karlsen , T M , Høgberg , N-W and van Nieuwenhove , R . 2008 . “ Results from irradiation assisted stress corrosion cracking and stress relaxation studies preformed in the Halden reactor ” . In Proceedings of the 6th International Symposium Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 581 – 590 . SFEN . A144
  • Hash , M C , Busby , J T and Was , G S . 2004 . “ The effect of hardening source in proton irradiation-assisted stress corrosion cracking of cold worked type 304 stainless steel ” . In Effects of Radiation on Materials: 21st International Symposium, ASTM STP 1447 , 92 – 104 . ASTM .
  • Fukuya , K , Nishioka , H , Fujii , K , Kamaya , M , Miura , T and Torimaru , T . 2009 . “ Material property changes of stainless steels under PWR irradiation ” . In Proceedings of the 2009 International Congress on Advances in Nuclear Power Plants , Tokyo : ICAPP'09 . May 10–14; Paper 9191
  • Fukuya , K. , Nakano , M , Fujii , K and Torimaru , T . 2004 . Role of radiation-induced grain boundary segregation in irradiation assisted stress corrosion cracking . J Nucl Sci Technol , 41 : 594 – 600 . doi: 10.1080/18811248.2004.9715522
  • Busby , J T , Was , G S and Kenik , E A . 2002 . Isolation of the role of radiation-induced segregation in IASCC of proton-irradiated austenitic stainless steels . J Nucl Mater , 302 : 20 – 40 . doi: 10.1016/S0022-3115(02)00719-5
  • Thomas , L E and Bruemmer , S M . 2002 . “ Analytical transmission electron microscopy characterization of stress corrosion cracks in an irradiated type 316 stainless steel core component ” . In Proceedings of the 5th International Symposium Fontevraud 5, Contribution of Materials Investigations to the Resolution of Problems Encountered in Pressurized Water Reactors , 347 – 360 . SFEN .
  • Thomas , L E and Bruemmer , S M . 2003 . “ Microstructural and microchemical characterization of intergranular stress corrosion cracks in irradiated type 304SS removed from a BWR top guide ” . In Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1049 – 1059 . ANS . [CD-ROM]
  • Thomas , L , Edwards , D and Asano , K . 2007 . “ Crack-tip characteristics in BWR service components ” . In Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Fukuya , K , Nishioka , H , Fujii , K and Kitsunai , Y . 2009 . “ Characterization of IASCC crack tip in highly irradiated stainless steels ” . In Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1248 – 1258 . ANS . [CD-ROM]
  • Manahan , M P , Kohli , R , Santucci , J and Sipush , P . 1989 . A phenomenological investigation of in-reactor cracking of type 304 stainless steel control rod cladding . Nucl Eng Design , 113 : 297 – 321 . doi: 10.1016/0029-5493(89)90024-1
  • Matsuoka , T , Yonezawa , T , Tomimatsu , M , Mori , M , Myojin , H , Sasaki , Y , Ootani , M and Nagata , T . 1995 . Intergranular cracking in cladding tube of PWR RCCA rodlets . JSME Int J , A38 : 515 – 523 .
  • Morisawa , J , Kodama , M , Yokota , N , Nakata , K , Fukuya , K , Shima , S and Asano , K . 2001 . Hydrogen analysis and slow strain rate test in Ar gas for irradiated austenitic stainless steel . J Nucl Mater , 294 : 241 – 249 . doi: 10.1016/S0022-3115(01)00494-9
  • Fukuya , K , Nishioka , H , Fujii , K , Kamaya , M , Miura , T and Torimaru , T . 2008 . Fracture behavior of austenitic stainless steels irradiated in PWR . J Nucl Mater , 378 : 211 – 219 . doi: 10.1016/j.jnucmat.2008.06.028
  • McMurtrey , M D , Was , G S , Patrick , L and Farkas , D . 2011 . Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy . Mater Sci Eng , A528 : 3730 – 3740 .
  • West , E A and Was , G S . 2011 . A model for the normal stress dependence of intergranular cracking of irradiated 316L stainless steel in supercritical water . J Nucl Mater , 408 : 142 – 152 . doi: 10.1016/j.jnucmat.2010.11.012
  • Kamaya , M , Kawamura , Y and Kitamura , T . 2007 . Three-dimensional local stress analysis on grain boundaries in polycrystalline material . Int J Solids Struct , 44 : 3267 – 3277 . doi: 10.1016/j.ijsolstr.2006.09.020
  • Fukuya , K , Nishioka , H , Fujii , K , Miura , T and Kitsunai , Y . 2013 . Local strain distribution near grain boundaries under tensile stresses in highly irradiated SUS316 stainless steel . J Nucl Mater , 432 : 67 – 71 . doi: 10.1016/j.jnucmat.2012.08.038
  • Evrad , P and Sauzay , M . 2010 . Modelling of the effect of dislocation channel on intergranular microcrack nucleation in pre-irradiated austenitic stainless steels during low strain rate tensile loading . J Nucl Mater , 405 : 83 – 94 . doi: 10.1016/j.jnucmat.2010.06.006
  • Sauzay , M , Bavard , K and Karlsen , W . 2010 . TEM observations and finite element modelling of channel deformation in pre-irradiated austenitic stainless steels - Interaction with free surfaces and grain boundaries . J Nucl Mater , 406 : 152 – 165 . doi: 10.1016/j.jnucmat.2010.01.027
  • Kim , Y J . 1999 . Analysis of oxide film formed on type 304 stainless steel in 288C water containing oxygen, hydrogen, and hydrogen peroxide . Corrosion , 55 : 81 – 88 . doi: 10.5006/1.3283969
  • Stellwag , B . 1998 . The mechanism of oxide film formation on austenitic stainless steels in high-temperature water . Corros Sci , 40 : 337 – 380 . doi: 10.1016/S0010-938X(97)00140-6
  • Terachi , T , Yamada , T , Miyamoto , T , Arioka , K and Fukuya , K . 2008 . Corrosion behavior of stainless steels in simulated PWR primary water -Effect of chromium content in alloys and dissolved hydrogen- . J Nucl Sci Technol , 45 : 975 – 984 . doi: 10.1080/18811248.2008.9711883
  • Shoji , T , Lu , Z , Das , N K , Murakami , H , Takeda , Y and Ismail , T . 2009 . “ Modeling stress corrosion cracking growth rates based upon the effect of stress/strain on crack tip interface degradation and oxidation kinetics ” . In Proceedings of the ASME 2009 Pressure Vessels and Piping Division Conference, PVP2009 , ASME . PVP2009-77615
  • Arioka , K , Yamada , T , Terachi , T and Miyamoto , T . 2008 . Dependence of stress corrosion cracking for cold-worked stainless steel on temperature and potential, and role of diffusion of vacancies at crack tips . Corrosion , 64 : 691 – 705 . doi: 10.5006/1.3278507
  • Sharkawy , S W , Xia , Z and Szklarska-Smialowska , Z . 1992 . Stress corrosion cracking of AISI 304 and 316 stainless steels in lithiated water at 350°C . J Nucl Mater , 195 : 184 – 190 . doi: 10.1016/0022-3115(92)90375-U
  • Jiao , Z and Was , G . 2011 . “ Oxidation of a proton-irradiated 316 stainless steel in simulated BWR NWC environment ” . In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1329 – 1338 . TMS . [CD-ROM]
  • Nishioka , H , Fukuya , K , Fujii , K and Kitsunai , Y . 2012 . Analyses of surface oxides formed on irradiated stainless steels in simulated primary water . J Institute Safety System , 19 : 131 – 143 . [in Japanese]
  • Li , G F , Kaneshima , Y and Shoji , T . 2000 . Effects of impurities on environmentally assisted crack growth of solution-annealed austenitic steels in primary water at 325°C . Corrosion , 56 : 460 – 468 . doi: 10.5006/1.3280550
  • Andresen , P L and Morra , M M . 2005 . “ Effects of Si on SCC of irradiated and unirradiated stainless steels and nickel alloys ” . In Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 87 – 106 . TMS . [CD-ROM]
  • Busby , J T and Was , G S . 2003 . “ Irradiation assisted stress corrosion cracking in model austenitic alloys with solute additions ” . In Proceedings of the 11th International Conference Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 995 – 1012 . ANS . [CD-ROM]
  • Jacobs , A J . 1987 . “ Hydrogen buildup in irradiated type-304 stainless steel ” . In Influence of Radiation on Material Properties: 13th International Symposium, ASTM STP 956 , 239 – 244 . ASTM .
  • Matsuoka , T , Yamaguchi , Y , Yonezawa , T , Nakamura , K , Fukuda , R and Shiraishi , S . 1999 . Irradiation assisted mechanical cracking on cladding tubes of control rods in nuclear reactors . JSME Int J , A42 : 438 – 446 . doi: 10.1299/jsmea.42.438
  • Morisawa , J , Kodama , M , Nishimura , S , Asano , K , Nakata , K and Shima , S . 1994 . Effects of hydrogen on mechanical properties in irradiated austenitic stainless steels . J Nucl Mater , 212–215 : 1396 – 1400 . doi: 10.1016/0022-3115(94)91057-X
  • Chung , H M , Strain , R V , Perry , D L and Shack , W J . 2003 . “ Irradiation-assisted cracking of austenitic stainless steels in water and in inert environment ” . In Proceedings of the 11th International Conference Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 1164 – 1174 . ANS . [CD-ROM]
  • Birnbaum , H K and Sofronia , P . 1994 . Hydrogen-enhanced localized plasticity – a mechanism for hydrogen-related fracture . Mater Sci Eng , A176 : 191 – 202 .
  • Robertson , I M . 1999 . The effect of hydrogen on dislocation dynamics . Eng Fract Mech , 64 : 649 – 673 . doi: 10.1016/S0013-7944(99)00094-6
  • Miura , T , Fujii , K , Nishioka , H and Fukuya , K . Effects of hydrogen on interaction between dislocations and radiation-induced defects in austenitic stainless steels. . J Nucl Mater , In press.
  • Bennetch , J I and Jesser , W A . 1981 . Microstructural aspects of He embrittlement in type 316 stainless steel . J Nucl Mater , 103&104 : 809 – 813 . doi: 10.1016/0022-3115(82)90699-7
  • Miura , T . 2012 . “ Micro tensile testing for He-implanted stainless steel ” . In Presented in NuMat 2012: The Nuclear Materials Conference Osaka 22-25 Oct
  • Yamagushi , M , Shiga , M and Kaburaki , H . 2004 . Energetics of segregation and embrittling potency for non-transition elements in the Ni Σ5 (012) symmetrical tilt grain boundary: a first-principal study . J Phys Cond Matter , 16 : 3933 – 3956 . doi: 10.1088/0953-8984/16/23/013
  • Yamaguchi , M , Shiga , M and Kaburaki , H . 2006 . Grain boundary decohesion by sulfur segregation in ferromagnetic iron and nickel – a first-principles study . Mater Trans , 47 : 2682 – 2689 . doi: 10.2320/matertrans.47.2682
  • Yamaguchi , M and Kaburaki , H . 2007 . “ First-principles calculations on the grain boundary decohesion of iron and nickel by oxygen ” . In Proceedings of the Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications , ANS .
  • Pathania , R , Carter , R and Demma , A . 2010 . “ Overview of EPRI research on effects of irradiation on LWR internals ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A102. [CD-ROM]
  • Fukuya , K , Fujii , K , Takakura , K and Nakata , K . 2010 . A prediction model of IASCC initiation stress for bolts in PWR core internals . Nucl Eng Design , 240 : 473 – 481 . doi: 10.1016/j.nucengdes.2009.10.022
  • Fujii , K , Fukuya , K , Furutani , G , Torimaru , T , Kohyama , A and Katoh , Y . 2001 . “ Swelling in 316 stainless steel irradiated to 53dpa in a PWR ” . In Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , NACE . [CD-ROM]
  • Foster , J P , Porter , D L , Harrod , D L , Mager , T R and Burke , M G . 1995 . 316 stainless steel cavity swelling in a PWR . J Nucl Mater , 224 : 207 – 215 . doi: 10.1016/0022-3115(95)00086-0
  • Garner , F A , Toloczko , M B , Porollo , S I , Vorobjev , A N , Dvoriashin , A M and Konobeev , Y uV . 1995 . “ Potential irradiation creep and void swelling of stainless steels in PWR internals ” . In Proceedings of the 8th International Symposium Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors , 839 – 845 . ANS .
  • Porollo , S I , Vorobjev , A N , Konobeev , Y uV , Dvoriashin , A M , Krigan , V M , Budylkin , N I , Mironova , E G and Garner , F A . 1998 . Swelling and void-induced embrittlement of austenitic stainless steel irradiated to 73–82 dpa at 335–336°C . J Nucl Mater , 258–263 : 1613 – 1617 . doi: 10.1016/S0022-3115(98)00166-4
  • Maksimkin , O P , Tsai , K V , Turubarova , L G , Doronina , T and Garner , F A . 2004 . Characterization of 08Cr16Ni11Mo3 stainless steel irradiated in the BN-350 reactor . J Nucl Mater , 329–333 : 625 – 629 . doi: 10.1016/j.jnucmat.2004.04.102
  • Garner , F A and Makenas , B J . 2007 . “ Recent experimental results on neutron-induced void swelling of AISI 304 stainless steel concerning its interactive dependence on temperature and displacement rate ” . In Proceedings of the 6th International Symposium Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 625 – 636 . SFEN . A032
  • Hamada , S , Maziasz , P J , Tanaka , M P , Suzuki , M and Hishinuma , A . 1988 . Temperature dependence of swelling in type 316 stainless steel . J Nucl Mater , 155–157 : 838 – 844 . doi: 10.1016/0022-3115(88)90426-6
  • Thomas , L E and Beeston , J M . 1982 . The microstructure of neutron irradiated type 348 stainless steel and its relation to creep and hardening . J Nucl Mater , 107 : 159 – 167 . doi: 10.1016/0022-3115(82)90418-4
  • Matsubara , T , Tsutsui , T , Kamei , Y and Kitsu , M . 2010 . “ Stress evaluation of baffle former bolt for IASCC failure prediction ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A069. [CD-ROM]
  • Torimaru , T , Kodama , M , Tanaka , S , Nakamura , T , Kumagai , K and Asano , K . 2010 . “ Fracture toughness of austenitic stainless steels after BWR irradiation ” . In Proceedings of the 7th International Symposium Fontevraud 7, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , SFEN . A060. [CD-ROM]
  • Jenssen , A , Grigoriev , V , Jakobsson , R and Efsing , P . 2007 . “ Fracture resistance evaluation of a flux thimble irradiated to 65 dpa in a PWR ” . In Proceedings of the 6th International Symposium Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 649 – 660 . SFEN . A030
  • Ehrnstén , U , Wallin , K , Roikonen , P K , van Dyck , S and Ould , P . 2007 . “ Fracture toughness of stainless steels irradiated up to ∼9 dpa in commercial BWRs ” . In Proceedings of the 6th International Symposium Fontevraud 6, Contribution of Materials Investigations to Improve the Safety and Performance of LWRs , 661 – 670 . SFEN . A034
  • Heera , M L , Higgins , J P , Hattori , S , Andou , M , Akiyama , M , Suzuki , I , Koyama , M , Chujo , N , Kanazawa , Y and Okubo , T . 1996 . “ Evaluation of the effects of radiation on the fracture toughness of BWR components ” . In Proceedings of the International Conference on Nuclear Engineering , Vol. 5 , ASME .
  • Xu , H , Fyfitch , S and Tang , H T . 2007 . “ Fracture toughness behavior of irradiated stainless steel in PWR system ” . In Proceedings of the 13th International Conference Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , CNS . [CD-ROM]
  • Carter , R G and Gamble , R M . 2002 . “ Assessment of the fracture toughness of irradiated stainless steel for BWR core shrouds ” . In Proceedings of the 5th International Symposium Fontevraud 5, Contribution of Materials Investigations to Resolution of Problems Encountered in Pressurized Water Reactors , 381 – 392 . SFEN .
  • Hamilton , M L , Garner , F A and Yang , W JS . 1986 . Prediction of fracture toughness in irradiated AISI 316 based on a tensile toughness correlation . Fusion Technol , 10 : 405 – 410 .
  • Wolfer , W G and Jones , R H . 1981 . Flow and fracture of alloys in the fusion environment . J Nucl Mater , 103&104 : 1305 – 1314 . doi: 10.1016/0022-3115(82)90780-2

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.