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

Keep up to date with the latest research on this topic with citation updates for this article.

Read on this site (6)

Terumitsu Miura, Katsuhiko Fujii, Koji Fukuya & Hitoshi Seto. (2022) Micro-mechanical investigation about degradation of grain boundary cohesive strength of neutron-irradiated stainless steels. Journal of Nuclear Science and Technology 59:10, pages 1251-1265.
Read now
Liuming Wan, Liang Chen & Zhengcao Li. (2021) Ab initio calculations of interaction between Ni and Si in α-Fe. Journal of Nuclear Science and Technology 58:2, pages 201-206.
Read now
Toshiki Nakasuji & Kazunori Morishita. (2020) Statistical arguments towards the development of an advanced embrittlement correlation method for reactor pressure vessel materials. Journal of Nuclear Science and Technology 57:3, pages 312-322.
Read now
Li Liu, Kenji Nishida, Kenji Dohi, Akiyoshi Nomoto, Naoki Soneda, Kenta Murakami, Zhengcao Li, Dongyue Chen & Naoto Sekimura. (2016) Effects of solute elements on hardening and microstructural evolution in neutron-irradiated and thermally-aged reactor pressure vessel model alloys. Journal of Nuclear Science and Technology 53:10, pages 1546-1553.
Read now
Kenta Murakami, Naoto Sekimura, Takeo Iwai & Hiroaki Abe. (2016) Heterogeneity of ion irradiation-induced hardening in A533B reactor pressure vessel model alloys. Journal of Nuclear Science and Technology 53:7, pages 1061-1066.
Read now
Bai Cui, Michael D. McMurtrey, Gary S. Was & Ian M. Robertson. (2014) Micromechanistic origin of irradiation-assisted stress corrosion cracking. Philosophical Magazine 94:36, pages 4197-4218.
Read now

Articles from other publishers (124)

G.S. Was, C.-B. Bahn, J. Busby, B. Cui, D. Farkas, M. Gussev, M. Rigen He, J. Hesterberg, Z. Jiao, D. Johnson, W. Kuang, M. McMurtrey, I. Robertson, A. Sinjlawi, M. Song, K. Stephenson, K. Sun, S. Swaminathan, M. Wang & E. West. (2024) How irradiation promotes intergranular stress corrosion crack initiation. Progress in Materials Science 143, pages 101255.
Crossref
Wen Jiang, Yangyang Zhao, Yu Lu, Yaqiao Wu, David Frazer, Donna P. Guillen, David W. Gandy & Janelle P. Wharry. (2024) Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation. Journal of Nuclear Materials 594, pages 155018.
Crossref
Merbin John, Alessandro M. Ralls, Manoranjan Misra & Pradeep L. Menezes. (2024) Understanding the Mechanism of Stress Corrosion Cracking Resistance in Stainless Steel Welds Subjected to Laser Shock Peening without Coating for Nuclear Canister Applications. Journal of Materials Engineering and Performance 33:8, pages 3957-3977.
Crossref
Gábor Vértesy, Madalina Rabung, Antal Gasparics, Inge Uytdenhouwen, James Griffin, Daniel Algernon, Sonja Grönroos & Jari Rinta-Aho. (2024) Evaluation of the Embrittlement in Reactor Pressure-Vessel Steels Using a Hybrid Nondestructive Electromagnetic Testing and Evaluation Approach. Materials 17:5, pages 1106.
Crossref
Boris Margolin, Alexander Sorokin & Lyubov Belyaeva. (2024) A Link between Neutron and Ion Irradiation Hardening for Stainless Austenitic and Ferritic-Martensitic Steels. Metals 14:1, pages 99.
Crossref
Ghiath Monnet. (2023) Analytical flow equation for irradiated low-alloy steels established by multiscale modeling. Journal of Nuclear Materials 586, pages 154647.
Crossref
Srinivasan Swaminathan, Kai Sun & Gary S. Was. (2023) Decoupling the roles of grain boundary oxidation and stress in IASCC of neutron-irradiated 304L stainless steel. Journal of Nuclear Materials 585, pages 154604.
Crossref
Shengkai Wang, Shihao Zhang, Jiayu Xie, Miao Song & Wenjun Kuang. (2023) The time dependence of proton irradiation effect on the intergranular oxidation of 316 L stainless steel in high-temperature hydrogenated water. Acta Materialia 260, pages 119340.
Crossref
Kymbat M. Tynyshbayeva, Artem L. Kozlovskiy, Ruslan V. Rakhimov, Vladimir V. Uglov & Maxim V. Zdorovets. (2023) Study of The Gas-Swelling Mechanisms in Silicon Carbide Ceramics under High-Temperature Irradiation with Helium Ions. Materials 16:17, pages 5750.
Crossref
Mikihiro Sakata, Kota Kadoi & Hiroshige Inoue. (2023) Age-hardening behaviors of the weld metals of 22% Cr and 25% Cr duplex stainless steels at 400 °C. Journal of Nuclear Materials 581, pages 154438.
Crossref
Yeugeniy V. Bikhert, Artem L. Kozlovskiy, Anatoli I. Popov & Maxim V. Zdorovets. (2023) Study of the Influence of the Irradiation Flux Density on the Formation of a Defect Structure in AlN in the Case of the Effect of Overlapping of the Heavy Ion Motion Trajectories in the Near-Surface Layer. Materials 16:15, pages 5225.
Crossref
Boris Margolin, Natalia Pirogova, Alexander Sorokin, Vasiliy Kokhonov, Alexey Dub & Ivan Safonov. (2023) Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment. Materials 16:7, pages 2585.
Crossref
Mikihiro Sakata, Kota Kadoi & Hiroshige Inoue. (2022) Mechanism for enhanced age hardening of 22 % Cr duplex stainless steel weld metal fabricated with grade 2209 filler material. Materials Today Communications 33, pages 104201.
Crossref
T. Fujita, J. Hirabayashi, Y. Katayama, F. Kano & H. Watanabe. (2022) Contribution of dislocation loop to radiation-hardening of RPV steels studied by STEM/EDS with surveillance test pieces. Journal of Nuclear Materials 572, pages 154055.
Crossref
Saheed B. Adisa & Matthew J. Swenson. (2022) Temperature Shift for Nanocluster Evolution in Ion-Irradiated Ferritic-Martensitic Alloys. JOM 74:11, pages 4069-4080.
Crossref
Xiaodong Lin, Qunjia Peng, En-Hou Han & Wei Ke. (2022) Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water. Journal of Materials Science & Technology 120, pages 36-52.
Crossref
S.A. Karpov, G.D. Tolstolutskaya & A.S. Kalchenko. (2022) Effect of noble-gas bubbles on deuterium trapping behavior in argon pre-implanted stainless steel. Journal of Nuclear Materials 566, pages 153661.
Crossref
Xuejiao Wang, Wenjiang Qiang, Xi Jin, Junwei Qiao, Yucheng Wu & Peter K. Liaw. (2022) Remarkable embrittlement and its origins in quenched reactor pressure vessel steels. Journal of Nuclear Materials 565, pages 153770.
Crossref
B. Rossaert, T. Toyama, M. Yamazaki, K. Suzuki, M. Narui, T. Shikama, E. Sikik, P. Jacquet & S. Van Dyck. (2022) Development of a multipurpose rig for material irradiation tests in BR2. Journal of Nuclear Materials 565, pages 153742.
Crossref
Alvaro Rodríguez-Prieto, Manuel Callejas, Ernesto Primera, Guglielmo Lomonaco & Ana María Camacho. (2022) Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels. Mathematics 10:10, pages 1779.
Crossref
C.N. Niu, W.L. Zhou, X.G. Song, S.P. Hu, J. Cao, M.X. Yang & W.M. Long. (2022) Surface modification of pure aluminum via Ar ion bombardment for Al/Al solid-state diffusion bonding. Materials Characterization 187, pages 111886.
Crossref
Wenjun Kuang, Xingyu Feng, Donghai Du, Miao Song, Mi Wang & Gary S. Was. (2022) A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water. Corrosion Science 199, pages 110187.
Crossref
Ken-ichi Fukumoto, Kohei Umehara & Kiyohiro Yabuuchi. (2022) Dynamic Interaction between Dislocation and Irradiation-Induced Defects in Stainless Steels during Tensile Deformation. Metals 12:5, pages 762.
Crossref
Wang Zijun, Du Xiaoming, Li Tianfu, Sun Kai, Tong Xuezhu, Li Meijuan, Liu Rongdeng, Liu Yuntao & Chen Dongfeng. (2022) Investigation of Cu-enriched precipitates in thermally aged Fe-Cu and Fe-Cu-Ni model alloys. Journal of Nuclear Materials 562, pages 153601.
Crossref
Jingfan Yang, Laura Hawkins, Miao Song, Lingfeng He, Mukesh Bachhav, Qingyu Pan, Lin Shao, Daniel Schwen & Xiaoyuan Lou. (2022) Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking. Journal of Nuclear Materials 560, pages 153493.
Crossref
Zhouran Zhang, David E.J. Armstrong & Patrick S. Grant. (2022) The effects of irradiation on CrMnFeCoNi high-entropy alloy and its derivatives. Progress in Materials Science 123, pages 100807.
Crossref
Peng Wang, Karsten Nowotka & Gary S. Was. (2022) Reproducing shadow corrosion on Zircaloy-2 using in-situ proton irradiation. Journal of Nuclear Materials 558, pages 153406.
Crossref
Terumitsu Miura, Katsuhiko Fujii, Koji Fukuya & Masahiro Kawakubo. (2021) Characterization of hardening behavior of carbon steels at low temperature irradiations. Journal of Nuclear Materials 557, pages 153270.
Crossref
Hisashi Takamizawa, Kuniki Hata, Yutaka Nishiyama, Takeshi Toyama & Yasuyoshi Nagai. (2021) The role of silicon on solute clustering and embrittlement in highly neutron-irradiated pressurized water reactor surveillance test specimens. Journal of Nuclear Materials 556, pages 153203.
Crossref
T. Toyama, C. Zhao, T. Yoshiie, S. Yamasaki, S. Uno, M. Shimodaira, H. Miyata, T. Suzudo, Y. Shimizu, K. Yoshida, K. Inoue & Y. Nagai. (2021) Radiation-enhanced diffusion of copper in iron studied by three-dimensional atom probe. Journal of Nuclear Materials 556, pages 153176.
Crossref
B. Z. Margolin, N. E. Pirogova, A. A. Sorokin & V. I. Kokhonov. (2021) Mechanisms of Stress Corrosion Cracking of Irradiated Austenitic Chromium–Nickel Steels Used for WWER and PWR Vessel Internals. Inorganic Materials: Applied Research 12:6, pages 1701-1720.
Crossref
Baolong Jiang, Binglu Zhang, Yang He, Qunjia Peng, Zhijie Jiao & Lijie Qiao. (2021) Combined effects of irradiation and hydrogen ions on surface oxidation of 308 L austenite stainless steel. Corrosion Science 191, pages 109734.
Crossref
E.A. Kuleshova, G.M. Zhuchkov, S.V. Fedotova, D.A. Maltsev, A.S. Frolov & I.V. Fedotov. (2021) Precipitation kinetics of radiation-induced Ni-Mn-Si phases in VVER-1000 reactor pressure vessel steels under low and high flux irradiation. Journal of Nuclear Materials 553, pages 153091.
Crossref
Boris Margolin, Natalia Pirogova, Alexander Sorokin & Anatoliy Morozov. (2021) Correlation between grain boundary strength determined by impact test of miniature specimen and stress corrosion cracking resistance of irradiated austenitic steels used for the internals of WWER-type and PWR-type nuclear reactors. Engineering Failure Analysis 127, pages 105544.
Crossref
D. A. Maltsev, E. A. Kuleshova, S. V. Fedotova, M. A. Saltykov & N. V. Stepanov. (2021) Application of the EBSD Method to Study the Fracture Mechanisms of Reactor Pressure Vessels Steels under Operational Factors. Crystallography Reports 66:4, pages 704-707.
Crossref
Boris Margolin, Victoria Shvetsova, Alexander Sorokin, Andrey Minkin & Natalia Pirogova. (2021) Mechanisms of plastic deformation and fracture of austenitic chromium-nickel steel irradiated during 45 years in WWER-440. Journal of Nuclear Materials 549, pages 152911.
Crossref
Timothy G. Lach, Matthew J. Olszta, Sandra D. Taylor, Kayla H. Yano, Dan J. Edwards, Thak Sang Byun, Peter H. Chou & Daniel K. Schreiber. (2021) Correlative STEM-APT characterization of radiation-induced segregation and precipitation of in-service BWR 304 stainless steel. Journal of Nuclear Materials 549, pages 152894.
Crossref
Xuejiao Wang, Wenjiang Qiang, Guogang Shu, Junwei Qiao & Yucheng Wu. (2021) The ageing behavior and the correlation between hardness and coercivity of Cu-rich reactor pressure vessel model steels. Journal of Magnetism and Magnetic Materials 527, pages 167698.
Crossref
Malcolm Griffiths. (2021) Effect of Neutron Irradiation on the Mechanical Properties, Swelling and Creep of Austenitic Stainless Steels. Materials 14:10, pages 2622.
Crossref
B. Z. Margolin, A. A. Sorokin, V. A. Shvetsova, A. J. Minkin & N. E. Pirogova. (2021) Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 4. Mechanical properties and fracture mechanisms. Voprosy Materialovedeniya:1(105), pages 116-144.
Crossref
Yinan Cui, Nasr Ghoniem & Giacomo Po. (2021) Plasticity of irradiated materials at the nano and micro-scales. Journal of Nuclear Materials 546, pages 152746.
Crossref
Donghai Du, Kai Sun & Gary S. Was. (2021) IASCC of neutron irradiated 316 stainless steel to 125 dpa. Materials Characterization 173, pages 110897.
Crossref
Peng Wang, Slavica Grdanovska, David M. Bartels & Gary S. Was. (2021) Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry. Journal of Nuclear Materials 545, pages 152744.
Crossref
M. McMurtrey, C. Sun, R.E. Rupp, C.-H. Shiau, R. Hanbury, N. Jerred & R. O'Brien. (2021) Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility. Journal of Nuclear Materials 545, pages 152739.
Crossref
V.A. Zheltonozhsky, D.E. Myznikov, V.I. Slisenko, M.V. Zheltonozhskaya & A.P. Chernyaev. (2021) Determination of the long-lived 10Be in construction materials of nuclear power plants using photoactivation method. Journal of Environmental Radioactivity 227, pages 106509.
Crossref
David Blanchet, Muriel Antony, Hubert Carcreff, Sébastien François, Philippe Guimbal & Bernard Pouchin. (2021) Assessment of Irradiation Performance in the Jules Horowitz Reactor (JHR) using the CARMEN Measuring Device. EPJ Web of Conferences 253, pages 04010.
Crossref
Nguyen Huu Tiep, Sy Minh Tuan Hoang, Donny Hartanto, Kyung Doo Kim, Jong Kyung Kim, Nguyen Minh Tuan & Pham Nhu Viet Ha. (2020) Investigation of the VVER-1000 reactor pressure vessel neutron fluence and displacement per atom using MCNP6. Radiation Physics and Chemistry 177, pages 109141.
Crossref
Kenta Murakami. (2020) Influence of copper precipitates on clustering behavior of alloying elements observed in Japanese reactor pressure vessel surveillance materials using atom probe tomography. Journal of Nuclear Materials 542, pages 152508.
Crossref
Miao Song, Kevin G. Field, Richard M Cox & Gary S. Was. (2020) Microstructural characterization of cold-worked 316 stainless steel flux thimble tubes irradiated up to 100 dpa in a commercial Pressurized Water Reactor. Journal of Nuclear Materials 541, pages 152400.
Crossref
Liang Chen, Kenta Murakami, Dongyue Chen, Hiroaki Abe, Zhengcao Li & Naoto Sekimura. (2020) In situ transmission electron microscopy study of growth of dislocation loops in Fe-Ni alloy under ion irradiation. Scripta Materialia 187, pages 453-457.
Crossref
C. R. Arganis-Juárez, T. L. Rosas-Flores, A. K. Arias-Alcántara, N. F. Garza-Montes-de-Oca & R. Colás. (2020) Simulation of Neutron Irradiation Damage in Stainless Steel by Cold Rolling. Journal of Materials Engineering and Performance 29:10, pages 6912-6918.
Crossref
Renato Altobelli Antunes & Mara Cristina Lopes de Oliveira. (2020) Stress Corrosion Cracking of Structural Nuclear Materials: Influencing Factors and Materials Selection. Innovations in Corrosion and Materials Science (Formerly Recent Patents on Corrosion Science) 10:1, pages 5-24.
Crossref
Dongyue Chen, Kenta Murakami, Liang Chen, Zhengcao Li & Naoto Sekimura. (2020) An investigation of nucleation sites for the formation of solute clusters in ferrite Fe. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 478, pages 182-186.
Crossref
B. Z. Margolin, N. E. Pirogova, A. A. Sorokin & V. I. Kokhonov. (2020) Mechanisms of stress corrosion cracking of irradiated austenitic chromium-nickel steels used for WWER and PWR vessel internals. Voprosy Materialovedeniya:2(102), pages 174-199.
Crossref
B. Z. Margolin, A. M. Morozov, N. E. Pirogova & M. N. Grigoriev. (2020) Strength assessment of austenitic steel grain boundaries by impact bending tests for miniature specimens. Voprosy Materialovedeniya:2(102), pages 164-173.
Crossref
Yufeng Du, Kenta Yoshida, Yusuke Shimada, Takeshi Toyama, Koji Inoue, Kazuto Arakawa, Tomoaki Suzudo, Konstantinovic J. Milan, Robert Gerard, Somei Ohnuki & Yasuyoshi Nagai. (2020) In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing. Materialia 12, pages 100778.
Crossref
E.A. Kuleshova, S.V. Fedotova, B.A. Gurovich, A.S. Frolov, D.A. Maltsev, N.V. Stepanov, B.Z. Margolin, A.J. Minkin & A.A. Sorokin. (2020) Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals. Journal of Nuclear Materials 533, pages 152124.
Crossref
Peng Wang, Slavica Grdanovska, David M. Bartels & Gary S. Was. (2020) Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water. Journal of Nuclear Materials 533, pages 152108.
Crossref
T. Toyama, T. Yamamoto, N. Ebisawa, K. Inoue, Y. Nagai & G.R. Odette. (2020) Effects of neutron flux on irradiation-induced hardening and defects in RPV steels studied by positron annihilation spectroscopy. Journal of Nuclear Materials 532, pages 152041.
Crossref
Boris Margolin, Alexander Sorokin, Natalia Pirogova, Aki Toivonen, Faiza Sefta & Cédric Pokor. (2020) Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation. Engineering Failure Analysis 107, pages 104235.
Crossref
Hans-Peter Seifert, John Hickling & Derek Lister. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 129 189 .
Yoosung Ha, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa & Yutaka Nishiyama. (2019) Ion-induced irradiation hardening of the weld heat-affected zone in low alloy steel. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 461, pages 276-282.
Crossref
G.R. Odette, T. Yamamoto, T.J. Williams, R.K. Nanstad & C.A. English. (2019) On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models. Journal of Nuclear Materials 526, pages 151863.
Crossref
Ke Xu, Marc H. Weber, Yue Cao, Weilin Jiang, Dan J. Edwards, Bradley R. Johnson & John S. McCloy. (2019) Ion irradiation induced changes in defects of iron thin films: Electron microscopy and positron annihilation spectroscopy. Journal of Nuclear Materials 526, pages 151774.
Crossref
E. A. Kuleshova, D. A. Mal’tsev & S. V. Fedotova. (2019) Grain Boundary Embrittlement of Steels of Vver-1000 Reactor Vessels Under Long-Term Operation. Metal Science and Heat Treatment 61:7-8, pages 463-471.
Crossref
Liang Chen, Kenji Nishida, Kenta Murakami, Dongyue Chen, Li Liu, Tomohiro Kobayashi, Zhengcao Li & Naoto Sekimura. (2019) A model to evaluate the hardening effect of solute clusters in Fe-based alloys. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 455, pages 32-34.
Crossref
B. Z. Margolin, A. A. Sorokin, N. E. Pirogova, V. A. Potapova, Aki Toivonen, Faiza Sefta & Cédric Pokor. (2019) Model of corrosion cracking of irradiated austenitic steels. Part 2. Determination of model parameters and its verification. Voprosy Materialovedeniya:2(98), pages 178-190.
Crossref
B. Z. Margolin, A. A. Sorokin, N. E. Pirogova, V. A. Potapova, Aki Toivonen, Faiza Sefta & Cédric Pokor. (2019) Model of corrosion cracking of irradiated austenitic steels. Part 1. Analysis of damage mechanisms and formulation of the defining. Voprosy Materialovedeniya:2(98), pages 154-177.
Crossref
Liang Chen, Zhengcao Li, Li Liu, Naoto Sekimura & Naoki Soneda. (2019) Study of the effect of Ni on solute clustering in α-Fe. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 453, pages 28-31.
Crossref
Baolong Jiang, Tao Guo, Qunjia Peng, Zhijie Jiao, Alex A. Volinsky, Lei Gao, Yuan Ma & Lijie Qiao. (2019) Proton irradiation effects on the electron work function, corrosion and hardness of austenitic stainless steel phases. Corrosion Science 157, pages 498-507.
Crossref
Guanhong Lei, Sida Yang, Hefei Huang, Qing Huang, Renduo Liu, Wei Zhang, Guojun Yu & Long Yan. (2019) Corrosion-driven outward migration and growth of helium bubbles in a nickel-based alloy in high-temperature molten salt environment. Corrosion Science 153, pages 47-52.
Crossref
Álvaro Rodríguez-Prieto, Ana María Camacho & Miguel Ángel Sebastián. (2017) Selection of candidate materials for reactor pressure vessels: Application of irradiation embrittlement prediction models and a stringency level methodology. Proceedings of the Institution of Mechanical Engineers, Part L: Journal of Materials: Design and Applications 233:5, pages 965-976.
Crossref
C.R. Lear, M. Song, M. Wang & G.S. Was. (2019) Dual ion irradiation of commercial and advanced alloys: Evaluating microstructural resistance for high dose core internals. Journal of Nuclear Materials 516, pages 125-134.
Crossref
Ghiath Monnet, Ludovic Vincent & Lionel Gélébart. (2019) Multiscale modeling of crystal plasticity in Reactor Pressure Vessel steels: Prediction of irradiation hardening. Journal of Nuclear Materials 514, pages 128-138.
Crossref
Miao Song, Mi Wang, Xiaoyuan Lou, Raul B. Rebak & Gary S. Was. (2019) Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels. Journal of Nuclear Materials 513, pages 33-44.
Crossref
Dongyue Chen, Kenta Murakami, Hiroaki Abe, Zhengcao Li & Naoto Sekimura. (2019) Investigation of interactions between defect clusters in stainless steels by in situ irradiation at elevated temperatures. Acta Materialia 163, pages 78-90.
Crossref
Tim Williams & Randy Nanstad. 2019. Structural Alloys for Nuclear Energy Applications. Structural Alloys for Nuclear Energy Applications 411 483 .
Ghiath Monnet & Ludovic Vincent. 2019. Handbook of Mechanics of Materials. Handbook of Mechanics of Materials 167 197 .
M. N. Gussev, G. S. Was, J. T. Busby & K. J. Leonard. 2019. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2289 2300 .
Yasuhiro Chimi, Shigeki Kasahara, Hitoshi Seto, Yuji Kitsunai, Masato Koshiishi & Yutaka Nishiyama. 2019. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2255 2270 .
Justin R. Hesterberg, Zhijie Jiao & Gary S. Was. 2019. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2231 2242 .
Yimeng Chen, Yan Dong, Emmanuelle Marquis, Zhijie Jiao, Justin Hesterberg, Gary Was & Peter Chou. 2019. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2189 2207 .
Takuya Fukumura, Koji Fukuya, Katsuhiko Fujii, Terumitsu Miura & Yuji Kitsunai. 2019. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2153 2163 .
Baolong Jiang, Qunjia Peng, Zhijie Jiao, Alex Volinsky & Lijie Qiao. (2018) Proton Irradiation Effects on Hardness and the Volta Potential of Welding 308L Duplex Stainless Steel. Micromachines 10:1, pages 11.
Crossref
S.V. Fedotova, E.A. Kuleshova, B.A. Gurovich, A.S. Frolov, D.A. Maltsev, G.M. Zhuchkov & I.V. Fedotov. (2018) APT-studies of phase formation features in VVER-440 RPV weld and base metal in irradiation-annealing cycles. Journal of Nuclear Materials 511, pages 30-42.
Crossref
B. A. Gurovich, E. A. Kuleshova, D. A. Mal’tsev, Yu. M. Semchenkov, A. S. Frolov, Ya. I. Shtrombakh & A. V. Shutikov. (2018) Mechanism of Change In VVER-440, -1000 Vessel Material Properties in Irradiation–Recovery Annealing–Irradiation Cycle. Atomic Energy 125:2, pages 95-102.
Crossref
B. Z. Margolin, N. E. Pirogova, V. A. Potapova, A. A. Sorokin, N. V. Bardashova, S. N. Petrov & M. S. Mikhailov. (2019) Study of Steel Corrosion Cracking Mechanisms for VVER RPV Internals Based on Simulation Tests. Inorganic Materials: Applied Research 9:6, pages 1221-1236.
Crossref
Miao Song, Calvin R. Lear, Chad M. Parish, Mi Wang & Gary S. Was. (2018) Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization. Journal of Nuclear Materials 510, pages 396-413.
Crossref
Petra Bublíková, Patricie Halodová, Miroslav Fokt, Hygreeva Kiran Namburi, Vít Rosnecký, Jan Procházka, Jan Duchoň & Dalibor Vojtěch. (2018) Neutron Irradiated Reactor Internals: An Applied Methodology for Specimen Preparation and Post Irradiation Examination by Electron Microscopy Methods. Manufacturing Technology 18:4, pages 545-551.
Crossref
Masaki Shimodaira, Takeshi Toyama, Kenta Yoshida, Koji Inoue, Naoki Ebisawa, Keiko Tomura, Toshimasa Yoshiie, Milan J. Konstantinović, Robert Gérard & Yasuyoshi Nagai. (2018) Contribution of irradiation-induced defects to hardening of a low-copper reactor pressure vessel steel. Acta Materialia 155, pages 402-409.
Crossref
P.O. Barrioz, J. Hure & B. Tanguy. (2018) Void growth and coalescence in irradiated copper under deformation. Journal of Nuclear Materials 502, pages 123-131.
Crossref
Takeshi Toyama & Kenta Yohida. (2018) Recent development of nano/micro-scale analytical techniques for nuclear materials(1)原子力材料評価のための最新ナノミクロ分析技術の新展開. Journal of the Atomic Energy Society of Japan 60:4, pages 231-235.
Crossref
Liang Chen, Kenji Nishida, Kenta Murakami, Li Liu, Tomohiro Kobayashi, Zhengcao Li & Naoto Sekimura. (2018) Effects of solute elements on microstructural evolution in Fe-based alloys during neutron irradiation following thermal ageing. Journal of Nuclear Materials 498, pages 259-268.
Crossref
Ghiath Monnet & Ludovic Vincent. 2018. Handbook of Mechanics of Materials. Handbook of Mechanics of Materials 1 32 .
Mo-Rigen He, Drew C. Johnson, Gary S. Was & Ian M. Robertson. (2017) The role of grain boundary microchemistry in irradiation-assisted stress corrosion cracking of a Fe-13Cr-15Ni alloy. Acta Materialia 138, pages 61-71.
Crossref
Huibin Ke, Peter Wells, Philip D. Edmondson, Nathan Almirall, Leland Barnard, G. Robert Odette & Dane Morgan. (2017) Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels. Acta Materialia 138, pages 10-26.
Crossref
Anna Hojná. (2017) Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels. Metals 7:10, pages 392.
Crossref
J. An, J. Chen, G. Gou, H. Chen & W. Wang. (2017) Prediction of corrosion fatigue crack initiation behavior of A7N01P-T4 aluminum alloy welded joints. International Journal of Modern Physics B 31:16-19, pages 1744034.
Crossref
Qiaofeng Lu, Qing Su, Fei Wang, Chenfei Zhang, Yongfeng Lu, Michael Nastasi & Bai Cui. (2017) Influence of laser shock peening on irradiation defects in austenitic stainless steels. Journal of Nuclear Materials 489, pages 203-210.
Crossref
Kenta Murakami, Takeo Iwai, Hiroaki Abe & Naoto Sekimura. (2016) Interaction between solute atoms and radiation defects in Fe-Ni-Si and Fe-Mn-Si alloys under irradiation with proton ions at low-temperature. Journal of Nuclear Materials 482, pages 47-52.
Crossref
Kale J. Stephenson & Gary S. Was. (2016) The role of dislocation channeling in IASCC initiation of neutron irradiated stainless steel. Journal of Nuclear Materials 481, pages 214-225.
Crossref
Yasuhiro Chimi, Hisashi Takamizawa, Shigeki Kasahara, Keiko Iwata & Yutaka Nishiyama. (2016) Bayesian nonparametric analysis of crack growth rates in irradiated austenitic stainless steels in simulated BWR environments. Nuclear Engineering and Design 307, pages 411-417.
Crossref
Hisashi Takamizawa, Hiroto Itoh & Yutaka Nishiyama. (2016) Statistical analysis using the Bayesian nonparametric method for irradiation embrittlement of reactor pressure vessels. Journal of Nuclear Materials 479, pages 533-541.
Crossref
J. Hure, S. El Shawish, L. Cizelj & B. Tanguy. (2016) Intergranular stress distributions in polycrystalline aggregates of irradiated stainless steel. Journal of Nuclear Materials 476, pages 231-242.
Crossref
G. Meric de Bellefon & J.C. van Duysen. (2016) Tailoring plasticity of austenitic stainless steels for nuclear applications: Review of mechanisms controlling plasticity of austenitic steels below 400 °C. Journal of Nuclear Materials 475, pages 168-191.
Crossref
Yasuhiro Chimi, Yuji Kitsunai, Shigeki Kasahara, Kazuhiro Chatani, Masato Koshiishi & Yutaka Nishiyama. (2016) Correlation between locally deformed structure and oxide film properties in austenitic stainless steel irradiated with neutrons. Journal of Nuclear Materials 475, pages 71-80.
Crossref
Alan J. Ardell & Pascal Bellon. (2016) Radiation-induced solute segregation in metallic alloys. Current Opinion in Solid State and Materials Science 20:3, pages 115-139.
Crossref
Ying Yang, Kevin G. Field, Todd R. Allen & Jeremy T. Busby. (2016) Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe–Cr–Ni alloys. Journal of Nuclear Materials 473, pages 35-53.
Crossref
K. Fujii & K. Fukuya. (2016) Irradiation-induced microchemical changes in highly irradiated 316 stainless steel. Journal of Nuclear Materials 469, pages 82-88.
Crossref
L. Tan, R. E. Stoller, K. G. Field, Y. Yang, H. Nam, D. Morgan, B. D. Wirth, M. N. Gussev & J. T. Busby. (2015) Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions. JOM 68:2, pages 517-529.
Crossref
B.A. Gurovich, E.A. Kuleshova, A.S. Frolov, D.A. Maltsev, K.E. Prikhodko, S.V. Fedotova, B.Z. Margolin & A.A. Sorokin. (2015) Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels. Journal of Nuclear Materials 465, pages 565-581.
Crossref
M.D. McMurtrey, B. Cui, I. Robertson, D. Farkas & G.S. Was. (2015) Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel. Current Opinion in Solid State and Materials Science 19:5, pages 305-314.
Crossref
J. Hure, C. Vaille, P. Wident, D. Moinereau, C. Landron, S. Chapuliot, C. Benhamou & B. Tanguy. (2015) Warm PreStress effect on highly irradiated reactor pressure vessel steel. Journal of Nuclear Materials 464, pages 281-293.
Crossref
Jae-Hyeok Shim, Erwin Povoden-Karadeniz, Ernst Kozeschnik & Brian D. Wirth. (2015) Modeling precipitation thermodynamics and kinetics in type 316 austenitic stainless steels with varying composition as an initial step toward predicting phase stability during irradiation. Journal of Nuclear Materials 462, pages 250-257.
Crossref
Josh Kacher, Bai Cui & Ian M. Robertson. (2015) In situ and tomographic characterization of damage and dislocation processes in irradiated metallic alloys by transmission electron microscopy. Journal of Materials Research 30:9, pages 1202-1213.
Crossref
Kevin G. Field, Ying Yang, Todd R. Allen & Jeremy T. Busby. (2015) Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments. Acta Materialia 89, pages 438-449.
Crossref
Terumitsu Miura, Katsuhiko Fujii & Koji Fukuya. (2015) Micro-mechanical investigation for effects of helium on grain boundary fracture of austenitic stainless steel. Journal of Nuclear Materials 457, pages 279-290.
Crossref
Kale J. Stephenson & Gary S. Was. (2015) Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons. Journal of Nuclear Materials 456, pages 85-98.
Crossref
Boris Margolin, Alexander Sorokin, Valeriy Smirnov & Vera Potapova. (2015) Physical and mechanical modeling and prediction of fracture strain and fracture toughness of irradiated austenitic steels. Engineering Failure Analysis 47, pages 283-298.
Crossref
B. Gómez-Ferrer, I. García-Cortés, J. F. Marco, D. Jiménez-Rey & R. Vila. (2014) Decoupling of defect and short-range order contributions to resistivity recovery measurements in binary alloys. Physical Review B 90:22.
Crossref
Boris Margolin, Alexander Sorokin, Valeriy Smirnov & Vera Potapova. (2014) Physical and mechanical modelling of neutron irradiation effect on ductile fracture. Part 1. Prediction of fracture strain and fracture toughness of austenitic steels. Journal of Nuclear Materials 452:1-3, pages 595-606.
Crossref
M.D. McMurtrey, G.S. Was, B. Cui, I. Robertson, L. Smith & D. Farkas. (2014) Strain localization at dislocation channel–grain boundary intersections in irradiated stainless steel. International Journal of Plasticity 56, pages 219-231.
Crossref
B. Cui, J. Kacher, M. McMurtrey, G. Was & I.M. Robertson. (2014) Influence of irradiation damage on slip transfer across grain boundaries. Acta Materialia 65, pages 150-160.
Crossref
Yoshiharu Murase, Norikazu Yamamoto, Tadashi Shinohara, Akira Tahara, Toshiho Ogata & Kazuhiro Kimura. (2014) In-Beam Stress Corrosion Tests for Welded 308 Stainless Steel in Pure Water at 473 K. MATERIALS TRANSACTIONS 55:9, pages 1445-1450.
Crossref

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.