Citation: | Yuan Pan, Wang Haoyu, Huang Shan, Liu Menglong, Yue Ti, Ren Quanyao, Qin Mian, Zheng Lele, Guo Zixuan. Research on Thermal-fluid-structure Coupling Behavior for U-10Mo/Al Fuel Assemblies under Irradiation[J]. Nuclear Power Engineering, 2023, 44(S2): 11-16. doi: 10.13832/j.jnpe.2023.S2.0011 |
[1] |
KIM Y S, HOFMAN G L. Fission product induced swelling of U–Mo alloy fuel[J]. Journal of Nuclear Materials, 2011, 419(1-3): 291-301. doi: 10.1016/j.jnucmat.2011.08.018
|
[2] |
KIM Y S, HOFMAN G L, CHEON J S, et al. Fission induced swelling and creep of U–Mo alloy fuel[J]. Journal of Nuclear Materials, 2013, 437(1-3): 37-46. doi: 10.1016/j.jnucmat.2013.01.346
|
[3] |
YAN F, JIAN X B, DING S R. Effects of UMo irradiation creep on the thermo-mechanical behavior in monolithic UMo/Al fuel plates[J]. Journal of Nuclear Materials, 2019, 524: 209-217. doi: 10.1016/j.jnucmat.2019.07.006
|
[4] |
JO D, PARK J, CHAE H. Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors[J]. Progress in Nuclear Energy, 2014, 71: 39-51. doi: 10.1016/j.pnucene.2013.11.006
|
[5] |
LI L F, FANG D, ZHANG D L, et al. Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements[J]. Annals of Nuclear Energy, 2019, 134: 284-298. doi: 10.1016/j.anucene.2019.06.030
|
[6] |
KENNE J C, SOLBREKKEN G L. Coupled fluid structure interaction (FSI) modeling of parallel plate assemblies[C]//Proceedings of the ASME 2011 International Mechanical Engineering Congress and Exposition. Denver: American Society of Mechanical Engineers, 2011: 159-167.
|
[7] |
RICE A. Intercode advanced fuels and cladding comparison using BISON, FRAPCON, and FEMAXI fuel performance codes[D]. Columbia: University of South Carolina, 2015.
|
[8] |
HE Y N, CHEN P, WU Y W, et al. Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way[J]. Nuclear Engineering and Design, 2018, 328: 27-35.
|
[9] |
LIU R, ZHOU W Z. Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor[J]. Annals of Nuclear Energy, 2017, 109: 298-309. doi: 10.1016/j.anucene.2017.05.037
|
[10] |
SCHULTHESS J L, LLOYD W R, RABIN B, et al. Mechanical properties of irradiated U-Mo alloy fuel[J]. Journal of Nuclear Materials, 2019, 515: 91-106. doi: 10.1016/j.jnucmat.2018.12.025
|
[11] |
MARCHBANKS M F. ANS materials databook: ORNL/M-4582[R]. Oak Ridge: Oak Ridge National Lab. , 1995.
|
[12] |
OZALTUN H, SHEN M H H, MEDVEDEV P. Assessment of residual stresses on U10Mo alloy based monolithic mini-plates during Hot Isostatic Pressing[J]. Journal of Nuclear Materials, 2011, 419(1-3): 76-84. doi: 10.1016/j.jnucmat.2011.08.029
|