Verification and Validation of the Advanced Neutronics Component Program KYLIN V2.0 Based on B&W Critical Experiment Benchmark Task
-
摘要: KYLIN V2.0是中国核动力研究设计院自主研发的先进中子学组件程序，程序分别采用子群共振方法、特征线方法、切比雪夫有理近似方法进行共振、输运、燃耗计算，从而提供多群截面库。本文采用B&W临界实验基准题对于KYLIN V2.0程序进行验证确认，包括了B&W1484临界基准题21个算例、B&W1810临界基准题23个算例等。计算结果表明，KYLIN V2.0程序计算结果与测量数据吻合较好，验证了KYLIN V2.0程序具有较好计算精度与非均匀计算能力。
-
关键词:
- B&W临界实验基准题 /
- 中子学组件程序 /
- KYLIN V2.0 /
- 验证与确认
Abstract: KYLIN V2.0 is an advanced neutronics component program independently developed by the Nuclear Power Institute of China. The program uses subgroup resonance method, characteristic line method and Chebyshev rational approximation method to calculate resonance, transport and burnup, so as to provide multi-group cross-section library. This paper uses B&W critical experiment benchmark task to verify and validate the KYLIN V2.0 program, including 21 examples of B&W1484 critical benchmark task and 23 examples of B&W1810 critical benchmark task. The calculation results show that the calculation results of KYLIN V2.0 program are in good agreement with the measured data, which verifies that KYLIN V2.0 program has good calculation accuracy and non-uniform calculation ability. -
图 2 B&W1484临界实验基准题栅元结构
Figure 2. Cell Structure of B&W1484 Critical Experiment Benchmark Task
图 3 B&W1484临界实验基准题堆芯结构
Figure 3. Core Structure of B&W1484 Critical Experiment Benchmark Task
图 4 B&W1810临界实验基准题栅元结构
Figure 4. Cell Structurre of B&W1810 Critical Experiment Benchmark Task
图 5 B&W1810临界实验基准题堆芯结构
Figure 5. Core Structure of B&W1810 Critical Experiment Benchmark Task
图 6 B&W1810临界实验基准题内燃料区域结构示意图
Figure 6. Schematic Diagram of Internal Fuel Area Structure of B&W1810 Critical Experiment Benchmark Task
图 7 B&W1810算例1裂变率计算结果与测量值对比
“—”—无数据
Figure 7. Computed and Measured Results of Fission Rate of B&W1810 Example 1
图 8 B&W1810算例5裂变率计算结果与测量值对比
“—”—无数据
Figure 8. Computed and Measured Results of Fission Rate of B&W1810 Example 5
表 1 B&W1484临界实验基准题特征值计算结果
Table 1. Eigenvalue Results of B&W1484 Critical Experiment Benchmark Task
算例 结果 偏差/10−5 算例 结果 偏差/10−5 1 0.99879 −121 12 0.99949 −51 2 1.00033 33 13 1.00002 2 3 0.99908 −92 14 1.00016 16 4 1.00039 39 15 0.99952 −48 5 1.00011 11 16 0.99955 −45 6 1.00029 29 17 0.99861 −139 7 0.99875 −125 18 0.99911 −89 8 1.00053 53 19 0.99893 −107 9 1.00004 4 20 0.99875 −125 10 1.00119 119 21 0.99833 −167 11 1.00048 48 — — — “—”—无数据 
下载: 导出CSV
表 2 B&W1810临界实验基准题特征值计算结果
Table 2. Eigenvalue Results of B&W1810 Critical Experiment Benchmark Task
算例 结果 偏差/10−5 算例 结果 偏差/10−5 1 1.00017 17 9 0.99796 −204 2 0.99772 −218 10 0.99785 −215 3 1.00065 65 12 1.00047 47 4 0.99937 −63 13 0.99825 −175 5 0.99978 −22 14 1.00022 22 5A 0.99793 −207 15 0.99822 −178 5B 0.99753 −247 16 0.99820 −180 6 0.99845 −155 17 0.99840 −160 6A 0.99838 −162 18 1.00025 25 7 0.99787 −213 19 0.99841 −159 8 0.99790 −210 20 1.00047 47
下载: 导出CSV
-
[1] 谢仲生. 核反应堆物理分析[M]. 西安: 西安交通大学出版社, 2004: 139-164. [2] 谢仲生. 压水堆核电厂堆芯燃料管理计算及优化[M]. 北京: 中国原子能出版社, 2001: 21-47. [3] 柴晓明,涂晓兰,郭凤晨,等. 先进中子学栅格程序KYLIN-2的开发与初步验证[J]. 强激光与粒子束,2017, 27(1): 016016. doi: 10.11884/HPLPB201729.160306 [4] WANG D Y, PENG X J, YU Y R, et al. Description and verification of KYLIN-V2.0 lattice physics code[J]. Nuclear Engineering and Design, 2021, 379: 111132. [5] WEMPLE C A, GHEORGHIU H N M, STAMM’LER R J J, et al. Recent advances in the HELIOS-2 lattice physics code[C]//International Conference on the Physics of Reactors. Interlaken, Switzerland: Casino-Kursaal Conference Center, 2008. [6] CHOI S, KHASSENOV A, LEE D. Resonance self-shielding method using resonance interference factor library for practical lattice physics computations of LWRs[J]. Journal of Nuclear Science and Technology, 2015, 53(8): 1142-1154. [7] PENG S T, JIANG X F, ZHANG S H, et al. Subgroup method with resonance interference factor table[J]. Annals of Nuclear Energy, 2013, 59: 176-187. doi: 10.1016/j.anucene.2013.04.005 [8] GAO Z J, XU Y L, DOWNAR T J. The treatment of resonance interference effects in the subgroup method[J]. Annals of Nuclear Energy, 2011, 38(5): 995-1003. doi: 10.1016/j.anucene.2011.01.019 [9] ASKEW J. A characteristics formulation of the neutron transport equation in complicated geometries: AEEW-M 1108[R]. Winfrith: United Kingdom Atomic Energy Establishment, 1972. [10] LIANG L, WU H C, CAO L Z, et al. Development of a two-dimensional modularity characteristics code for neutron transport calculation[C]//2013 21st International Conference on Nuclear Engineering. Chengdu, China: ASME, 2013. [11] ZHAO C, LIU Z Y, LIANG L, et al. Improved leakage splitting method for the 2D/1D transport calculation[J]. Progress in Nuclear Energy, 2018, 105: 202-210. doi: 10.1016/j.pnucene.2018.01.007 [12] WANG D A, XIAO S C. A linear prolongation approach to stabilizing CMFD[J]. Nuclear Science and Engineering, 2018, 190: 45-55. doi: 10.1080/00295639.2017.1417347 [13] RAHNEMA F, NICHITA E M. Leakage corrected spatial (assembly) homogenization technique[J]. Annals of Nuclear Energy, 1997, 24(6): 477-488. doi: 10.1016/S0306-4549(96)00084-9 [14] PETROVIC I, BENOIST P, MARLEAU G. A quasi-isotropic reflecting boundary condition for the TIBERE heterogeneous leakage model[J]. Nuclear Science and Engineering, 1996, 122(2): 151-166. doi: 10.13182/NSE96-A24152 [15] PUSA M, LEPPÄNEN J. Computing the matrix exponential in burnup calculations[J]. Nuclear Science and Engineering, 2010, 164(2): 140-150. doi: 10.13182/NSE09-14 [16] NEWMAN L W. “Urania-Gadolinia”: Nuclear model development and critical experiment benchmark: DOE/ET/34212-41[R]. Lynchburg, VA, USA: Babcock & Wilcox, 1984. [17] BALDWIN M N, HOOVLER G S. Critical experiments supporting close proximity water storage of power reactor fuel: BAW-1484-6[R]. Lynchburg, USA: Babcock & Wilcox Company, 1979. -
计量
- 文章访问数: 271
- HTML全文浏览量: 56
- PDF下载量: 32
- 被引次数: 0
