Citation: | Liu Zhenhai, Zhou Yi, Qi Feipeng, Xin Yong, Li Wenjie, Gong Zhaohu, Zeng Wei, Zhang Tao. Study on Non-classical PCMI Behavior Based on FUPAC3D[J]. Nuclear Power Engineering, 2024, 45(S2): 77-83. doi: 10.13832/j.jnpe.2024.S2.0077 |
[1] |
STEPHANIE S. The consortium for advanced simulation of light water reactors[EB/OL].(2020-09-30) [2022-01-20]. https://www.casl.gov/wp-content/uploads/2020/11/CASL_FINAL_REPORT_09.30.2020-002.pdf.
|
[2] |
Idaho National Lab. The nuclear energy advanced modeling and simulation (NEAMS) program[EB/OL]. (2021-10-19)[2022-01-20]. http://neams.inl.gov.
|
[3] |
WILLIAMSON R L, HALES J D, NOVASCONE S R, et al. BISON: a flexible code for advanced simulation of the performance of multiple nuclear fuel forms[J]. Nuclear Technology, 2021, 207(7): 954-980. doi: 10.1080/00295450.2020.1836940
|
[4] |
TONKS M R, SCHWEN D, ZHANG Y, et al. Assessment of MARMOT. A mesoscale fuel performance code: INL/EXT-15-35108[R]. Idaho Falls, ID: INL, 2015.
|
[5] |
邢硕,张坤,陈平,等. 燃料棒性能分析程序FUPAC V2.0的研发与验证[J]. 原子能科学技术,2021, 55(11): 2048-2053. doi: 10.7538/yzk.2020.youxian.0925
|
[6] |
BERNARD L C, JACOUD J L, VESCO P. An efficient model for the analysis of fission gas release[J]. Journal of Nuclear Materials, 2002, 302(2-3): 125-134. doi: 10.1016/S0022-3115(02)00793-6
|
[7] |
ROSS A M, STOUTE R L. Heat transfer coefficient between UO2 and zircaloy-2: AECL-1552[R]. Chalk River, Ont: Atomic Energy of Canada Technical Report, 1962.
|
[8] |
OLANDER D R. Fundamental aspects of nuclear reactor fuel elements: TID-26711-P1, TRN: 08-019392[R]. Berkeley: University of California, Berkeley, 1976: 137-138.
|
[9] |
DUNNE F, PETRINIC N. Introduction to computational plasticity[M]. New York: Oxford University Press Inc. , 2005: 146-153.
|
[10] |
刘振海,陈平,周毅,等. 三维模拟芯块掉块对燃料性能的影响[J]. 核动力工程,2018, 39(2): 180-184.
|