References
- IAEA report on nuclear energy for a net zero world ahead of COP26 climate summit, 2021
- Makenas BJ. Swelling of 20% cold-worked type 316 stainless steel fuel pin cladding and ducts. In: Effects of radiation on materials 12th, ASTM STP. Vol. 870. 1985. p. 202–211. doi: 10.1520/STP37362S
- Fissolo A, Cauvin R, Hugot J-P et al. Influence of swelling on irradiated CW titanium modified 316 embrittlement. In: Packan NH, Stoller RE, Kumar AS, editors. Effects of radiation on materials 14th, ASTM STP 1046. 1990. p. 700–713. doi: 10.1520/STP1046-EB
- Seran JL, Levy L, Dubuisson P et al. Behavior under neutron irradiation of the 15-15Ti and EM10 steels used as standard materials of the Phenix fuel subassembly. In: Effects of Radiation on Materials 15th, ASTM STP 1125. 1992. p. 1209–1233. doi: 10.1520/STP17941S
- Baker RB, Bard FE, Leggett RD, et al. Status of fuel, blanket, and absorber testing in the fast flux test facility. J Nucl Mater. 1993;204:109–118. doi: 10.1016/0022-3115(93)90206-E
- Fissolo A, Levy V, Seran JL et al. Tensile properties of neutron irradiated 316Ti and 15-15Ti steels. In: Effects of Radiation on Materials 16th, ASTM STP 1175. 1994. p. 646–663. doi: 10.1520/STP23964S
- Maillard A, Touron H, Seran J-L et al. Swelling and irradiation creep of neutron irradiated 316Ti and 15-15Ti steels. In: Effects of Radiation on Materials 16th, ASTM STP 1175. 1994. p. 824–837. doi: 10.1520/STP23974S
- Uehira A, Ukai S, Mizuta S et al. Irradiation creep deformation of modified 316 and 15Cr-20Ni base austenitic fuel elements irradiated in FFTF. In: Effects of Radiation on Materials 20th, ASTM STP 1405. 2001. p. 487–499. doi: 10.1520/STP10552S
- Uwaba T, Ito M, Mizuno T. Irradiation performance of fast reactor MOX fuel Assemblies irradiated to high burnups. J Nucl Sci Technol. 2008;45(11):1183–1192. doi: 10.1080/18811248.2008.9711907
- Yamagata I, Akasaka N. Swelling behaviors in a fuel assembly for the wrapping wire and duct made of modified 316 austenitic stainless steel. J Nucl Sci Technol. 2010;47(10):898–907. doi: 10.1080/18811248.2010.9720969
- Was GS, Ukai S. Structural alloys for nuclear energy application. In: G.R. Odette and S.J. Zinkle, Eds. Elsevier; 2019. p. 293–347. doi: 10.1016/B978-0-12-397046-6.09991-3
- Uwaba T, Ukai S. Study on short term stress limit in fast reactor fuel pin designs. Nucl Eng Des. 2004;234:51–59.
- Shibahara I, Ukai S, Onose S et al. Irradiation performance of modified 316 stainless steel for Monju fuel. J Nucl Mater. 1993;204:131–140. doi: 10.1016/0022-3115(93)90209-H
- Yoshitake T, Ohmori T, Tanaka K, “Tensile properties of austenitic steel fuel claddings irradiated in FFTF as the Monju type fuel assemblies (MFA-1 & MFA-2)”, JNC research report, JNC TN9400 2001-116 [in Japanese]
- Aoyama T, Sekine T, Tabuchi S. Characterization of neutron field in the experimental fast reactor JOYO for fuel and structural material irradiation test. Nucl Eng Des. 2004;228:21–34. doi: 10.1016/j.nucengdes.2003.06.003
- Maeda S, Ito C, Ohkawachi Y et al. Characterization of neutron field in the experimental fast reactor JOYO MK-III core. Reactor Dosimetry State Of The Art. 2008. p. 474–482. ISBN 978-981-4271-10-3.
- Garner FA, Hamilton ML, Panayotou NF et al. The microstructural origins of yield strength changes in AISA 316 during fission or fusion irradiation. J Nucl Mater. 1981;104:803–808. doi: 10.1016/0022-3115(82)90698-5
- Lucas GE. The evolution of mechanical property change in irradiated austenitic stainless steels. J Nucl Mater. 1993;206(2–3):287–305. doi: 10.1016/0022-3115(93)90129-M
- Uwaba T, Maeda S, Mizuno T, et al. Study on the mechanism of diametral cladding strain and mixed-oxide fuel element breaching in slow-ramp extended overpower transients. J Nucl Mater. 2012;429(1–3):149–158. doi: 10.1016/j.jnucmat.2012.05.042
- Akasaka N, Hattori K, Onose S et al. Effect of temperature change on void swelling in P, Ti-modified 316 stainless steel. J Nucl Mater. 1999;271&272:370–375. doi: 10.1016/S0022-3115(98)00721-1
- Yamashita S, Tachi Y, Akasaka N, et al. Effect of neutron irradiation on the microstructure of modified SUS316 stainless steels. J Nucl Mater. 2011;417(1–3):953–957. doi: 10.1016/j.jnucmat.2010.12.187
- Rowcliffe AF, Hishinuma A, Grossbeck ML et al. Radiation effects at fusion reactor He: dpa rations: Overview of US/Japan Sectrally tailored experiments. J Nucl Mater. 1991;179-181:125–129. doi: 10.1016/0022-3115(91)90026-4
- Bennetch JI, Jesser WA. Microstructural aspect of He embrittlement in type 316 stainless steel. J Nucl Mater. 1981;103&104:809–814. doi: 10.1016/0022-3115(82)90699-7
- Kesternich W, Rothaut J. Reduction of helium embrittlement in stainless steel by finely dispersed TiC precipitates. J Nucl Mater. 1981;103&104:845–852. doi: 10.1016/0022-3115(82)90705-X
- Akasaka N, Yamagata I, Ukai S. Effects of irradiation environment of fast reactor’s fuel elements on void swelling in P, Ti-modified 316 stainless steel. In: Effects of Radiation on Materials 20th, ASTM STP 1405. 2001. p. 443–456. doi: 10.1520/STP10549S
- Uwaba T, Ukai S. The formulation of the PNC316 swelling design equation. JNC Research Report. 2003. JNC TN9400 2003-007 [in Japanese].
- Flinn JE, Kenfield TA, “Neutron swelling observations on austenitic stainless steels irradiated in EBR-II”, proceedings of the workshop on correlation of neutron and charged particle damage, Conf-760673. 1976. p. 253–289
- Hure J, Courcelle A, Turque I. A micromechanical analysis of swelling-induced embrittlement in neutron-irradiation austenitic stainless steels. J Nucl Mater. 2022;565:15373. doi: 10.1016/j.jnucmat.2022.153732
- Neustroev VS, Garner FA. Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling. J Nucl Mater. 2009;386-388:157–160. doi: 10.1016/j.jnucmat.2008.12.077