The effects of neutron radiation on nickel-based alloys

References

• T. Abram and S. Ion: ‘Generation-IV nuclear power: a review of the state of the science’, Energy Policy, 2008, 36, (12), 4323–4330. doi: 10.1016/j.enpol.2008.09.059
   Web of Science ®Google Scholar
• A. F. Rowcliffe, L. K. Mansur, D. T. Hoelzer and R. K. Nanstad: ‘Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors’, J. Nucl. Mater., 2009, 392, (2), 341–352.
   Google Scholar
• G. O. Hayner, E. L. Shaber, R. E. Mizia, P. A. Lessing, R. N. Wright, T. C. Totemeier, W. E. Windes, W. R. Corwin, T. D. Burchell, J. M. Corum, J. W. Klett, R. K. Nanstad, L. L. Snead, R. E. Stoller, P. L. Rittenhouse, R. W. Swindeman and D. F. Wilson: ‘Next generation nuclear plant materials selection and qualification program plan’, Idaho National Engineering Laboratory Report No. INEEL/EXT-03-001128 (Rev. 0), Idaho Falls, Idaho, November 7, 2003.
   Google Scholar
• T. Schulenberg, L. Leung, D. Brady, Y. Oka, K. Yamada, Y. Bae and G. Willermoz: ‘IAEA Report: IAEA-CN-164-5S06: Supercritical Water-Cooled Reactor (SCWR) Development through GIF Collaboration’, Technical report, IAEA.
   Google Scholar
• C. D. Judge, N. Gauquelin, L. Walters, M. Wright, J. I. Cole, J. Madden, G. A. Botton and M. Griffiths: ‘Intergranular fracture in irradiated Inconel X-750 containing very high concentrations of helium and hydrogen’, J. Nucl. Mater., 2015, 457, (2), 165–172. doi: 10.1016/j.jnucmat.2014.10.008
   Web of Science ®Google Scholar
• D. Chersola, G. Lomonaco and R. Marotta: ‘The VHTR and GFR and their use in innovative symbiotic fuel cycles’, Prog. Nucl. Energy, 2015, 83, 443–459. doi: 10.1016/j.pnucene.2014.12.005
   Web of Science ®Google Scholar
• S. Bortot, P. C. Camprini, G. Grasso and C. Artioli: ‘Conceptual core design study for a high-flux LFR demonstrator’, Prog. Nucl. Energy, 2012, 54, (1), 56–63. doi: 10.1016/j.pnucene.2011.09.001
   Web of Science ®Google Scholar
• C. Cabet and F. Rouillard: ‘Corrosion of high temperature metallic materials in VHTR’, J. Nucl. Mater., 2009, 392, (2), 235–242. doi: 10.1016/j.jnucmat.2009.03.029
   Web of Science ®Google Scholar
• O. D. Kazachkovskii: ‘Radiation swelling of materials’, Atomic Energy, 1996, 81, (2), 605–610. doi: 10.1007/BF02415665
   Web of Science ®Google Scholar
• F. A. Comprelli, H. J. Busboom and C. N. Spalaris: ‘Comparison of radiation damage studies and fuel cladding performance for Inconel-800’, Irradiation Effects in Structural Alloys for Thermal and Fast Reactors, ASTM STP 457, American Society for Testing and Materials, 1969, 400–413.
   Google Scholar
• T. Pollock and S. Tin: ‘Nickel-based superalloys for advanced turbine engines: chemistry, microstructure, and properties’, J. Propul. Power, 2006, 22, (2), 361–374. doi: 10.2514/1.18239
   Web of Science ®Google Scholar
• C. Judge, M. Griffiths, L. Walters, M. Wright, G. Bickel, O. Woo, M. Stewart, S. Douglas and F. Garner: ‘Embrittlement of nickel alloys in a CANDU reactor environment’, in ‘25th symposium on effects of radiation on nuclear materials’, (ed. T. Yamamoto), ASTM STP 1547, 161–175; 2011, West Conshohocken, PA, ASTM International, DOI 10.1520/STP104242.
   Google Scholar
• M. Griffiths, G. Bickel and S. Douglas: ‘Irradiation-induced embrittlement of Inconel 600 flux detectors in CANDU reactors’, J. Energy Power Eng., 2012, 6, 188–194.
   Google Scholar
• S. J. Zinkle and G. S. Was: ‘Materials challenges in nuclear energy’, Acta Mater., 2013, 61, (3), 735–758. doi: 10.1016/j.actamat.2012.11.004
   Web of Science ®Google Scholar
• K. L. Murty and I. Charit: ‘Structural materials for Gen-IV nuclear reactors: challenges and opportunities’, J. Nucl. Mater., 2008, 383, (1–2), 189–195. doi: 10.1016/j.jnucmat.2008.08.044
   Web of Science ®Google Scholar
• P. Ford, P. Combrade and P. Scott: ‘Degradation of Alloy 600 SG Tubes in Secondary PWR coolant, environmentally-assisted degradation of nickel-base alloys in LWRs’, 2011, Sweden, Advanced Nuclear Technology International.
   Google Scholar
• P. Scott, P. Combrade and P. Ford: ‘Environmentally-assisted degradation of nickel-base alloys in LWRs (Chapter 2.2.3.1)’, 2011, Sweden, Advanced Nuclear Technology International.
   Google Scholar
• H. K. Zhang, Z. Yao, M. A. Kirk and M. R. Daymond: ‘Stability of Ni3(Al, Ti) gamma prime precipitates in a nickel-based superalloy inconel X-750 under heavy ion irradiation’, Metall. Mater. Trans. A, 2014, 45, (8), 3422–3428. doi: 10.1007/s11661-014-2309-y
   Web of Science ®Google Scholar
• J. Dong, X. Liu, X. Xie and R. Thompson: ‘The segregation of sulfur and phosphorus in nickel-base Alloy 718’, Acta Metall. Sinica (English Letters), 2009, 10, (6), 510–514.
   Google Scholar
• A. L. Ward, J. M. Steicher and P. L. Knecht: ‘Irradiation effects on the microstructure and properties of metals’, 156; 1976, American Society for Testing and Materials, ASTM STP 611.
   Google Scholar
• T. T. Claudson and H. J. Pessl: ‘Irradiation effects on high-temperature reactor structural metals’, ASTM STP 380: Flow Fract. Metals Alloys Nucl. Environ., 1965 1, 156–171.
   Google Scholar
• J. Moteff, F. C. Robertshaw and F. D. Kingsbury: ‘Effects of neutron irradiation on the stress-rupture properties of high-temperature precipitation hardening alloys’, J. Nucl. Mater., 1965, 17, (3), 245–258. doi: 10.1016/0022-3115(65)90168-6
   Web of Science ®Google Scholar
• T. Claudson: ‘Effects of irradiation on structural materials’, ASTM STP, 1976, 426, 67.
   Google Scholar
• M. L. Bleiberg and J. W. Bennett: ‘Radiation effects in breeder reactor structural materials’, Technical report, American Institute of Mining, Metallurgical, and Petroleum Engineers, Inc., New York (1977).
   Google Scholar
• C. Cawthorne and E. J. Fulton: ‘Voids in irradiated stainless steel’, Nature, 1967, 216, 575–576. doi: 10.1038/216575a0
   Web of Science ®Google Scholar
• W. G. Johnston, J. H. Rosolowski, A. M. Turkalo and T. Lauritzen: ‘An experimental survey of swelling in commercial Fe-Cr-Ni alloys bombarded with 5 MeV Ni Ions’, J. Nucl. Mater., 1974, 54, (1), 24–40. doi: 10.1016/0022-3115(74)90073-7
   Web of Science ®Google Scholar
• J. Bates and W. Johnston: Proceedings of the international conference on radiation effects in breeder reactor structural materials, The Metallurgical Society of AIME, New York (1977) 625.
   Google Scholar
• R. L. Klueh and A. T. Nelson: ‘Ferritic/martensitic steels for next-generation reactors’, J. Nucl. Mater., 2007, 371, (13), 37–52. doi: 10.1016/j.jnucmat.2007.05.005
   Web of Science ®Google Scholar
• E. E. Bloom, J. O. Stiegler, A. F. Rowcliffe and J. M. Leitnaker: ‘Austenitic stainless steels with improved resistance to radiation-induced swelling’, Scripta Metall., 1976, 10, (4), 303–308. doi: 10.1016/0036-9748(76)90081-8
   Google Scholar
• P. Yvon and F. Carre: ‘Structural materials challenges for advanced reactor systems’, J. Nucl. Mater., 2009, 385, (2), 217–222. doi: 10.1016/j.jnucmat.2008.11.026
   Web of Science ®Google Scholar
• G. R. Gessel and C. L. White: ‘DOE Cladding/Duct Materials Development Quarterly Progress Report’, TC-160-18, Technical report (1978).
   Google Scholar
• H. Ullmaier: ‘Radiation damage in metallic materials’, MRS Bull., 1997, 22, 14–21.
   Web of Science ®Google Scholar
• L. R. Greenwood and F. A. Garner: ‘Hydrogen generation arising from the 59Ni (n, p) reaction and its impact on fission-fusion correlations’, J. Nucl. Mater., 1996, 233–237, 1530–1534. doi: 10.1016/S0022-3115(96)00264-4
   Web of Science ®Google Scholar
• F. Garner, L. Greenwood and B. Oliver: ‘A re-evaluation of helium/dpa and hydrogen/dpa ratios for fast reactor and thermal reactor data used in fission-fusion correlations’, Technical report, Proceeding of a Technical Committee Meeting, Obnisk, Russian Federation, IAEA-TECDOC-1039 (16–19 June,1997).
   Google Scholar
• L. Greenwood, F. Garner, B. Oliver, M. Grosseck and W. Wolfer: ‘Surprisingly large generation and retention of helium and hydrogen in pure nickel irradiated at high temperatures and high neutron exposures’, ASTM Int., 2006, 1, (4), 1–11, DOI 10.1520/JAI11365.
   Google Scholar
• S. J. Zinkle, W. G. Wolfer, G. L. Kulcinski and L. E. Seitzman: ‘Part II. Effect of oxygen and helium on void formation in metals’, Philos. Mag. A, 1987, 55, (1), 127–140. doi: 10.1080/01418618708209804
   Web of Science ®Google Scholar
• H. Schroeder and H. Ullmaier: ‘Helium and hydrogen effects on the embrittlement of iron- and nickel-based alloys’, J. Nucl. Mater., March–April 1991, 179–181, (1), 118–124.
   Web of Science ®Google Scholar
• F. Garner, B. Oliver, L. Greenwood, D. Edwards and S. Bruemmer: ‘Generation and retention of helium and hydrogen in austenitic steels irradiated in a variety of LWR and test reactor spectral environments’, Technical report, Pacific Northwest National Laboratory (PNNL), Richland, WA (US) (2002).
   Google Scholar
• C. H. Lund: ‘Physical metallurgy of nickel based superalloys’, Technical report, Battelle Memorial Inst. Defense Metals Information Center, Columbus, OH (1961).
   Google Scholar
• D. J. Tillack: ‘Selection of nickel, nickel-copper, nickel-chromium, and nickel-chromium-iron alloys’, Technical report, ASM Handbook Volume 6, Welding, Brazing, and Soldering (ASM International) (1993).
   Google Scholar
• Y. Yin, R. G. Faulkner, P. Moreton, I. Armson and P. Coyle: ‘Grain boundary chromium depletion in austenitic alloys’, J. Mater. Sci., 2010, 45, (21), 5872–5882. doi: 10.1007/s10853-010-4666-2
   Web of Science ®Google Scholar
• Y. Yin, F. Zhu, R. Faulkner, E. Miller, P. Moreton, I. Armson and B. Borradaile: ‘Predicting chromium depletion of nickel base alloys’, in ‘15th international conference on environmental degradation of materials in nuclear power systems-water reactors’ (eds. J. T. Busby, G. Ilevbare and P. L. Andresen), 2012, Hoboken, NJ, John Wiley & Sons, DOI 10.1002/9781118456835.ch32.
   Google Scholar
• R. Bajaj, W. Mills, M. Lebo, B. Hyatt and M. Burke: ‘Irradiation-assisted stress corrosion cracking of HTH Alloy X-750 and Alloy 625’, Seventh international symposium on environmental degradation of materials in nuclear power systems–water reactors, Vol. 2, 1093–1107; 1995, Brechenridge, CO, NACE.
   Google Scholar
• R. Baumann and T. Hossain: ‘Electronic device and process achieving a reduction in alpha particle emissions from boron-based compounds essentially free of boron-10’, US Patent 5,395,783, 7 March 1995.
   Google Scholar
• M. Kangilaski: ‘Effects of neutron radiation on structural materials’, Technical report, Battelle Memorial Inst., Columbus, Ohio. Radiation Effects Information Center (1967).
   Google Scholar
• F. Wiffen: ‘Response of Inconel 600 to simulated fusion reactor irradiation. Effects of radiation on structural materials’, ASTM STP, 1979, 683, 88.
   Google Scholar
• T. M. Angeliu, J. T. Ward and J. K. Witter: ‘Assessing the effects of radiation damage on Ni-base alloys for the Prometheus space reactor system’, J. Nucl. Mater., 2007, 366, (1), 223–237. doi: 10.1016/j.jnucmat.2007.01.217
   Web of Science ®Google Scholar
• M. I. Baskes: ‘Recent advances in understanding helium embrittlement in metals’, MRS Bull., 1986, 11, (4), 14–18. doi: 10.1557/S0883769400069116
   Google Scholar
• W. J. Mills: ‘Fracture toughness of two Ni-Fe-Cr alloys’, Eng. Fract. Mech., 1987, 26, (2), 223–238. doi: 10.1016/0013-7944(87)90199-8
   Web of Science ®Google Scholar
• C. Hunter, R. Fish and J. Holmes: ‘Channel fracture in irradiated EBR-II type 304 stainless steel’, Trans. Amer. Nucl. Soc., 1972, 15, 254–255.
   Google Scholar
• R. L. Fish: ‘Notch effect on the tensile properties of fast-reactor-irradiated type 304 stainless steel’, Nucl. Technol., 1976, 31, (1), 85–95.
   Web of Science ®Google Scholar
• L. A. James: ‘Effect of fast neutron irradiation on fatigue-crack growth behavior of three nickel-base alloys’, Nucl. Technol., 1981, 53, (1), 64–68.
   Web of Science ®Google Scholar
• J.-J. Kai and R. D. Lee: ‘Effects of proton irradiation on the microstructural and microchemical evolution of Inconel 600 alloy’, J. Nucl. Mater., 1993, 207, 286–294. doi: 10.1016/0022-3115(93)90271-Y
   Web of Science ®Google Scholar
• S. Porollo, Y. Konobeev, A. Dvoriashin, M. Alexander, V. Krigan and F. Garner: ‘Determination of the lower temperature limit of void swelling of stainless steels at relatively low displacement rates’, Technical report, Pacific Northwest National Laboratory (PNNL), Richland, WA (US) (2002).
   Google Scholar
• L. K. Mansur: ‘Effects of point defect trapping and solute segregation on irradiation-induced swelling and creep’, J. Nucl. Mater., 1979, 83, (1), 109–127. doi: 10.1016/0022-3115(79)90597-X
   Web of Science ®Google Scholar
• M. Kurban, U. Erb and K. T. Aust: ‘A grain boundary characterization study of boron segregation and carbide precipitation in Alloy 304 austenitic stainless steel’, Scripta Mater., 2006, 54, (6), 1053–1058. doi: 10.1016/j.scriptamat.2005.11.055
   Web of Science ®Google Scholar
• S. I Golubov, R. E. Stoller, S. J. Zinkle and A. M. Ovcharenko: ‘Kinetics of coarsening of helium bubbles during implantation and post-implantation annealing’, J. Nucl. Mater., 2007, 361, (2), 149–159. doi: 10.1016/j.jnucmat.2006.12.032
   Web of Science ®Google Scholar
• L. K. Mansur and K. Farrell: ‘On mechanisms by which a soft neutron spectrum may induce accelerated embrittlement’, J. Nucl. Mater., 1990, 170, (3), 236–245. doi: 10.1016/0022-3115(90)90294-W
   Web of Science ®Google Scholar
• P. L. Andresen, F. P. Ford, S. M. Murphy and J. M. Perks: ‘Modeling and prediction of irradiation assisted stress corrosion cracking’, Seventh international symposium on environmental degradation of materials in nuclear power systems – Water reactors, Vol. 2, 893–906; 1990, Brechenridge, CO, NACE.
   Google Scholar
• A. F. Rowcliffe and J. A. Horak: ‘Tensile properties and fracture behavior of irradiated nickel alloys’, Trans. Amer. Nucl. Soc., 1981, 38, 226.
   Google Scholar
• F. Huang and R. Fish: ‘Effects of radiation on materials’, ASTM STP, 1985, 870, 720.
   Google Scholar
• W. J. S. Yang and B. J. Makenas: ‘Effects of radiation on materials’, ASTM STP, 1985, 870, (2), 127.
   Google Scholar
• S. Vaidyanathan: ‘Effects of irradiation on structural materials’, ASTM STP, 1982, 782, 619.
   Google Scholar
• R. Bajaj: ‘Effects of radiation on materials’, ASTM STP, 1981, 725, 326.
   Google Scholar
• A. L. Chang: ‘Micro and macro mechanics of crack growth’, 1982, Warrenville, PA, Metallurgical Society of AIME.
   Google Scholar
• R. Boothby and D. Harries: ‘Proceedings of the international conference on mechanical behaviour and nuclear applications of stainless steel at elevated temperatures’, The Metals Society, London, 1982.
   Google Scholar
• R. M. Boothby: ‘The microstructure of fast neutron irradiated nimonic PE16’, J. Nucl. Mater., 1996, 230, (2), 148–157. doi: 10.1016/0022-3115(96)00169-9
   Web of Science ®Google Scholar
• G. Broomfield: ‘Irradiation effects in structural alloys for thermal and fast reactors’, ASTM STP, 1965, 457, 38.
   Google Scholar
• A. F. Rowcliffe: ‘Effects of radiation on structural metals’, ASTM STP, 1967, 426, 161.
   Google Scholar
• R. Nicholson and R. Jones: ‘Effects of radiation on materials’, ASTM STP, 1979, 683, 529.
   Google Scholar
• D. M. Symons: ‘A comparison of internal hydrogen embrittlement and hydrogen environment embrittlement of X-750’, Eng. Fract. Mech., 2001, 68, (6), 751–771. doi: 10.1016/S0013-7944(00)00123-5
   Web of Science ®Google Scholar
• J. Walsh and B. Rear: ‘Direct evidence for boron segregation to grain boundaries in a nickel-base alloy by secondary ion mass spectrometry’, Metall. Mater. Transact. A, 1975, 6, (1), 226–229. doi: 10.1007/BF02673697
   Web of Science ®Google Scholar
• A. Rowcliffe, G. Carpenter, H. Merrick and R. Nicholson: ‘An electron microscope investigation of high temperature embrittlement of irradiated stainless steels’, Effects Radiat. Struct. Mater. ASTM-STP, 1967, 426, 161–199. doi: 10.1520/STP41323S
   Google Scholar
• T. Allen and G. Was: ‘The effect of ordering on radiation-induced segregation in austenitic iron- and nickel-base alloys’, in ‘Effects of radiation on materials: 18th international symposium (STP 1325)’, (eds. R. K. Nanstad, M. L. Hamilton, F. A. Garner and A. S. Kumar), 619; 1999, West Conshohocken, PA, ASTM.
   Google Scholar
• J. Perks, A. Marwick and C. English: ‘Computer code to calculate radiation-induced segregation in concentrated ternary alloys’, AERE-R-12121, Technical report (1986).
   Google Scholar
• Y. Yang, K. Field and J. B. T. Allen: ‘Development of a robust modeling tool for radiation-induced segregation in austenitic stainless steels’, Technical report ORNL/TM-2015/479 (2015).
   Google Scholar
• L. Fournier, D. Delafosse and T. Magnin: ‘Cathodic hydrogen embrittlement in Alloy 718’, Mater. Sci. Eng. A, 1999, 269, (1–2), 111–119. doi: 10.1016/S0921-5093(99)00167-7
   Web of Science ®Google Scholar
• P. D. Hicks and C. J. Altstetter: ‘Hydrogen-enhanced cracking of superalloys’, Metall. Transact. A, 1992, 23, (1), 237–249. doi: 10.1007/BF02660868
   Web of Science ®Google Scholar
• M. A. Stopher and P. E. J. Rivera-Diaz-del-Castillo: ‘Hydrogen embrittlement in bearing steels’, Mater. Sci. Technol. 2016, 1–10 (online).
   Google Scholar
• E. V. Kornelsen and A. A. V. Gorkum: ‘A study of bubble nucleation in tungsten using thermal desorption spectroscopy: clusters of 2 to 100 helium atoms’, J. Nucl. Mater., 1980, 92, 79–88. doi: 10.1016/0022-3115(80)90144-0
   Web of Science ®Google Scholar
• G. Hultquist, M. J. Graham, J. L. Smialek and B. Jonsson: ‘Hydrogen in metals studied by thermal desorption spectroscopy (TDS)’, Corros. Sci., 2015, 93, 324–326. doi: 10.1016/j.corsci.2015.01.003
   Web of Science ®Google Scholar
• G. Young, N. Lewis, M. Hanson, W. Matuszyk, B. Wiersma and S. Gonzalez: ‘osti.govKAPL Report LM-01K034; Microstructural and microchemical characterization of dual step aged alloy X-750 and its relationship to environmentally assisted cracking’, Technical report (May 2001). osti.gov.
   Google Scholar
• H. Zhang, Z. Yao, M. R. Daymond and M. A. Kirk: ‘Cavity morphology in a Ni based superalloy under heavy ion irradiation with cold pre-injected helium’, J. Appl. Phys., 2014, 115, 103508.
   Google Scholar
• F. Garner and D. Gelles: ‘Effects of radiation on materials’, ASTM STP, 1990, 1046, (2), 673.
   Google Scholar
• C. San Marchi, B. Somerday and S. Robinson: ‘Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures’, Int. J. Hydr. Energy, 2007, 32, (1), 100–116. doi: 10.1016/j.ijhydene.2006.05.008
   Web of Science ®Google Scholar
• F. Fischer, J. Svoboda and E. Kozeschnik: ‘Interstitial diffusion in systems with multiple sorts of traps’, Model. Simul. Mater. Sci. Eng., 2013, 21, (2), 1–13. doi: 10.1088/0965-0393/21/2/025008
   Web of Science ®Google Scholar
• M. A. Stopher, P. Lang, E. Kozeschnik and P. E. J. Rivera-Diaz-del-Castillo: ‘Modelling hydrogen migration and trapping in steels’, Mater. Des. 2016, 106, 205–215, DOI 10.1016/j.matdes.2016.05.051.
   Google Scholar
• J. Kameda and C. J. McMahon: ‘Solute segregation and hydrogen-induced intergranular fracture in an alloy steel’, Metall. Transact. A, 1983, 14, (4), 903–911. doi: 10.1007/BF02644295
   Web of Science ®Google Scholar
• M. I. Baskes and V. Vitek: ‘Trapping of hydrogen and helium at grain boundaries in nickel: an atomistic study’, Metall. Transact. A, 1985, 16, (9), 1625–1631. doi: 10.1007/BF02663018
   Web of Science ®Google Scholar
• R. Sugano, K. Morishita, H. Iwakiri and N. Yoshida: ‘Effects of dislocation on thermal helium desorption from iron and ferritic steel’, J. Nucl. Mater., 2002, 307–311, 941–945. doi: 10.1016/S0022-3115(02)01098-X
   Web of Science ®Google Scholar
• Y. Zakaria: ‘Thermal desorption analysis of helium trapping in ion-implanted beryllium’, Open Access Dissertations and Theses. Paper 2371.
   Google Scholar
• G. J. Thomas, W. A. Swansiger and M. I. Baskes: ‘Low-temperature helium release in nickel’, J. Appl. Phys., 1979, 50, (11), 6942–6947. doi: 10.1063/1.325848
   Web of Science ®Google Scholar
• J. Ehrenberg, B. M. U. Scherzer and R. Behrisch: ‘Thermal desorption spectroscopy of He from Ni at and below saturation’, Radiat. Effects, 1983, 78, (1–4), 405–416. doi: 10.1080/00337578308207389
   Web of Science ®Google Scholar
• J. Barnaby, P. Barton, R. Boothby, A. Fraser and G. Slattery: ‘Post-irradiation mechanical properties of AISI type 316 steel and Nimonic PE16 alloy’, in ‘Conference on radiation effects in breeder reactor structural materials’, Scottsdale, AZ, 19–23 June (eds. M. L. Bleiberg and J. W. Bennett), 159–175; 1977, New York, American Institute of Mining, Metallurgical, and Petroleum Engineers..
   Google Scholar
• D. Harman: ‘Postirradiation tensile and creep-rupture properties of several experimental heats of incoloy 800 at 700 and 760°C’, Technical report, Oak Ridge National Lab., Tenn. (1968).
   Google Scholar
• L. K. Mansur: ‘Theoretical evaluation of a mechanism of precipitate-enhanced cavity swelling during irradiation’, Philos. Mag. A, 1981, 44, (4), 867–877. doi: 10.1080/01418618108239554
   Web of Science ®Google Scholar
• F. Garner: ‘Materials science and technology’, Nucl. Mater., 1994, 10A, (part 1), 420.
   Google Scholar
• J. C. Zhao, M. Larsen and V. Ravikumar: ‘Phase precipitation and time–temperature-transformation diagram of Hastelloy X’, Mater. Sci. Eng. A, 2000, 293, (1), 112–119. doi: 10.1016/S0921-5093(00)01049-2
   Web of Science ®Google Scholar
• K. Bhanu S. Rao, H. Schuster and G. R. Halford: ‘On massive carbide precipitation during high temperature low cycle fatigue in alloy 800H’, Scripta Metall. Mater., 1994, 31, (4), 381–386. doi: 10.1016/0956-716X(94)90004-3
   Web of Science ®Google Scholar
• Y. F. Yin, R. G. Faulkner and Z. Lu: ‘Irradiation-induced precipitation modelling of ferritic steels’, J. Nucl. Mater., 2009, 389, (2), 225–232. doi: 10.1016/j.jnucmat.2009.02.006
   Web of Science ®Google Scholar
• K. C. Russell: ‘Phase stability under irradiation’, Prog. Mater. Sci., 1984, 28, (3–4), 229–434. doi: 10.1016/0079-6425(84)90001-X
   Web of Science ®Google Scholar
• J. R. Lindgren: ‘Irradiation effects on high-temperature gas-cooled reactor structural materials’, Nucl. Technol., 1984, 66, (3), 607–618.
   Web of Science ®Google Scholar
• P. Caceras, B. Ralph, G. Allen and R. Wild: ‘Grain boundary segregation in Inconel 600’, Surf. Interf. Anal., 1988, 12, (3), 191–197. doi: 10.1002/sia.740120304
   Web of Science ®Google Scholar
• J. K. Heuer, P. R. Okamoto, N. Q. Lam and J. F. Stubbins: ‘Disorder-induced melting in nickel: implication to intergranular sulfur embrittlement’, J. Nucl. Mater., 2002, 301, (2), 129–141. doi: 10.1016/S0022-3115(02)00707-9
   Web of Science ®Google Scholar
• W. C. Johnson, J. E. Doherty, B. H. Kear and A. F. Giamei: ‘Confirmation of sulfur embrittlement in nickel alloys’, Scripta Metall., 1974, 8, 971–974. doi: 10.1016/0036-9748(74)90394-9
   Google Scholar
• B. J. Berkowitz and R. D. Kane: ‘The effect of impurity segregation on the hydrogen embrittlement of a high strength nickel base alloy in H2S environments’, Corrosion, 1980, 36, (1), 24–29. doi: 10.5006/0010-9312-36.1.24
   Web of Science ®Google Scholar
• E. Lee and L. Mansur: ‘Mechanisms of swelling suppression in cold-worked phosphorous-modified Fe-Ni-Cr alloys’, Philos. Mag. A, 1990, 61, (5), 733–749. doi: 10.1080/01418619008231945
   Web of Science ®Google Scholar
• T. Yamamoto, G. R. Odette, P. Miao, D. Hoelzer, J. Bentley, N. Hashimoto, H. Tanigawa and R. J. Kurtz: ‘The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates’, J. Nucl. Mater., 2007, 367, 399–410. doi: 10.1016/j.jnucmat.2007.03.047
   Web of Science ®Google Scholar
• Y. Gan, H. Zhao, D. T. Hoelzer and D. Yun: ‘Energetic study of helium cluster nucleation and growth in 14YWT through first principles’, Materials, 2016, 9, (1), 17. doi: 10.3390/ma9010017
   Web of Science ®Google Scholar
• D. T. Hoelzer, J. Bentley, M. A. Sokolov, M. K. Miller, G. R. Odette and M. Alinger: ‘Influence of particle dispersions on the high-temperature strength of ferritic alloys’, J. Nucl. Mater., 2007, 367, 166–172. doi: 10.1016/j.jnucmat.2007.03.151
   Web of Science ®Google Scholar
• P. D. Edmondson, C. M. Parish, Q. Li and M. K. Miller: ‘Thermal stability of nanoscale helium bubbles in a 14YWT nanostructured ferritic alloy’, J. Nucl. Mater., 2014, 445, (1–3), 84–90. doi: 10.1016/j.jnucmat.2013.10.024
   Web of Science ®Google Scholar
• D. T. Hoelzer , J. P. Shingledecker, R. L. Klueh, M. K. Miller and J. Bentley: ‘The microstructural stability of a ruptured thermal creep specimen of MA957’, DOE/ER-0313/44 (June 30, 2008) 53.
   Google Scholar
• H. Kronmüller and P. Vargas: ‘Binding energy of hydrogen-impurity complexes in nickel’, Philos. Mag. A, 1985, 51, (1), 59–70. doi: 10.1080/01418618508245269
   Web of Science ®Google Scholar
• S.-M. Lee and J.-Y. Lee: ‘The trapping and transport phenomena of hydrogen in nickel’, Metall. Transact. A, 1986, 17, (2), 181–187. doi: 10.1007/BF02643893
   Web of Science ®Google Scholar
• F. Jambon, L. Marchetti, M. Sennour, F. Jomard and J. Chene: ‘SIMS and TEM investigation of hydrogen trapping on implantation defects in a nickel-based superalloy’, J. Nucl. Mater., 2015, 466, 120–133. doi: 10.1016/j.jnucmat.2015.07.045
   Web of Science ®Google Scholar
• J. E. Angelo, N. R. Moody and M. I. Baskes: ‘Trapping of hydrogen to lattice defects in nickel’, Model. Simul. Mater. Sci. Eng., 1995, 3, (3), 289. doi: 10.1088/0965-0393/3/3/001
   Web of Science ®Google Scholar
• A. Turnbull, R. Ballinger, I. Hwang, M. Morra, M. Psaila-Dombrowski and R. Gates: ‘Hydrogen transport in nickel-base alloys’, Metall. Transact. A, 1992, 23, (12), 3231–3244. doi: 10.1007/BF02663432
   Web of Science ®Google Scholar
• D. Symons: ‘An investigation into the effects of hydrogen on the fracture and deformation behavior of alloy X-750’, PhD Thesis, (1994).
   Google Scholar
• N. Moody, S. Robinson, S. Myers and F. Greulich: ‘Deuterium concentration profiles in Fe- Ni- Co alloys electrochemically charged at room temperature’, Acta Metall., 1989, 37, (1), 281–290. doi: 10.1016/0001-6160(89)90286-1
   Google Scholar
• B. G. Pound: ‘The effect of aging on hydrogen trapping in precipitation-hardened alloys’, Corros. Sci., 2000, 42, (11), 1941–1956. doi: 10.1016/S0010-938X(00)00036-6
   Web of Science ®Google Scholar
• D. H. Lassila and H. K. Birnbaum: ‘Intergranular fracture of nickel: the effect of hydrogen-sulfur co-segregation’, Acta Metall., 1987, 35, (7), 1815–1822. doi: 10.1016/0001-6160(87)90127-1
   Google Scholar
• A. Thompson and I. Bernstein: ‘The role of metallurgical variables in hydrogen-assisted environmental fracture’, Adv. Corros. Sci. Technol., 1979, 7, 53–175.
   Google Scholar
• B. G. Pound: ‘A comparison of hydrogen ingress behavior in Alloys 625 and 716’, Scripta Metall. Mater., 1993, 29, (11), 1433–1438. doi: 10.1016/0956-716X(93)90332-M
   Web of Science ®Google Scholar
• L. Mansur, E. Lee, P. Maziasz and A. Rowcliffe: ‘Control of helium effects in irradiated materials based on theory and experiment’, J. Nucl. Mater., 1986, 141, 633–646. doi: 10.1016/0022-3115(86)90066-8
   Web of Science ®Google Scholar
• E. D. Ezugwu, Z. M. Wang and A. R. Machado: ‘The machinability of nickel-based alloys: a review’, J. Mater. Process. Technol., 1999, 86, (1–3), 1–16. doi: 10.1016/S0924-0136(98)00314-8
   Web of Science ®Google Scholar