Citation: | Zhang Cheng, Wan Chenghui. Study on Treatment Method of Environmental Effect of Hexagonal Assembly PWR[J]. Nuclear Power Engineering, 2024, 45(5): 45-52. doi: 10.13832/j.jnpe.2024.05.0045 |
[1] |
KOEBKE K. A new approach to homogenization and group condensation[C]//IAEA Technical Comittee Meeting on Homogenization Methods in Reactor Physics. Lugano, 1978.
|
[2] |
KOEBKE K. Advances in homogenization and dehomogenization[C]//Proceedings of the International Topical Meeting on Advances in Mathematical Methods for the Solution of Nuclear Engineering Problems. Munich, 1981.
|
[3] |
YAMAMOTO T. Monte Carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations[J]. Annals of Nuclear Energy, 2012, 50: 141-149. doi: 10.1016/j.anucene.2012.06.025
|
[4] |
汤春桃,黄灏,张少泓. 改进现行轻水堆组件均匀化方法的必要性[J]. 核科学与工程,2007, 27(4): 327-332. doi: 10.3321/j.issn:0258-0918.2007.04.007
|
[5] |
李文淮,刘志宏. 组件均匀化中的边界条件误差修正方法研究[J]. 核科学与工程,2011, 31(3): 199-206.
|
[6] |
张斌. 压水堆全堆芯Pin-by-pin均匀化计算方法研究[D]. 西安: 西安交通大学,2017.
|
[7] |
汤春桃. 中子输运方程特征线解法及嵌入式组件均匀化方法的研究[D]. 上海: 上海交通大学,2009.
|
[8] |
SHEN W, ALTIPARMAKOV D. Multicell correction method for treatment of heterogeneities in full-core calculation of CANDU-type Reactors[J]. Nuclear Science and Engineering, 2013, 174(2): 109-134. doi: 10.13182/NSE12-42
|
[9] |
BILODID Y, FRIDMAN E, LÖTSCH T. X2 VVER-1000 benchmark revision: Fresh HZP core state and the reference Monte Carlo solution[J]. Annals of Nuclear Energy, 2020, 144: 107558. doi: 10.1016/j.anucene.2020.107558
|
[10] |
SMITH K S. Spatial homogenization methods for light water reactor analysis[D]. Cambridge: Massachusetts Institute of Technology, 1980.
|
[11] |
TAHARA Y, KANAGAWA T, SEKIMOTO H. Two-dimensional baffle/reflector constants for nodal code in PWR core design[J]. Journal of Nuclear Science and Technology, 2000, 37(11): 986-995. doi: 10.1080/18811248.2000.9714982
|
[12] |
MITTAG S, PETKOV P T, GRUNDMANN U. Discontinuity factors for non-multiplying material in two-dimensional hexagonal reactor geometry[J]. Annals of Nuclear Energy, 2003, 30(13): 1347-1364. doi: 10.1016/S0306-4549(03)00070-7
|
[13] |
张程. 六角形组件压水堆堆芯物理计算改进方法及其应用[D]. 西安: 西安交通大学,2022.
|
[14] |
ZHANG C, WAN C H, CAO L Z, et al. Method research and engineering validation of the improved homogenization for the heavy reflector in VVER[J]. Annals of Nuclear Energy, 2022, 173: 109119. doi: 10.1016/j.anucene.2022.109119
|
[15] |
LI Y Z, ZHANG B, HE Q M, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice[J]. Nuclear Engineering and Design, 2018, 335: 432-440. doi: 10.1016/j.nucengdes.2018.05.030
|
[16] |
YANG W, WU H C, LI Y Z, et al. Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core[J]. Nuclear Engineering and Design, 2018, 337: 279-290. doi: 10.1016/j.nucengdes.2018.07.017
|
[17] |
HE Q M, ZHENG Q, LI J, et al. NECP-MCX: a hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems[J]. Annals of Nuclear Energy, 2021, 151: 107978. doi: 10.1016/j.anucene.2020.107978
|
[18] |
TASHAKOR S, ZARIFI E, NAMINAZARI M. Neutronic simulation of CAREM-25 small modular reactor[J]. Progress in Nuclear Energy, 2017, 99: 185-195. doi: 10.1016/j.pnucene.2017.05.016
|