Neutronics Influence Research on Axial Grid of PWR Fuel Assembly
-
摘要: 基于先进压水堆燃料管理软件Bamboo-C，分别提出了轴向格架非均匀建模方法和均匀建模方法。采用轴向格架的2种不同建模方法，对福清核电厂M310堆型的燃料组件进行建模分析，通过与堆芯实测数据进行对比，检验2种不同建模方法对临界硼浓度、轴向功率分布及轴向功率偏移的影响。数值结果表明，压水堆燃料组件轴向非均匀建模方法能够显著提高堆芯关键物理参数的计算精度。Abstract: The heterogeneous modeling method and homogenous modeling method have been respectively proposed for the axial grids based on the advanced fuel-management code for PWR named Bamboo-C. Based on these two different modeling methods for axial grids, modeling analysis for the fuel assemblies of M310 reactor in Fuqing Nuclear Power Plant is carried out. By comparing with the measured data of the reactor core, the effects of two different modeling methods on the critical boron concentration, axial power distribution and axial power offset are tested. The numerical results show that the axial heterogeneous modeling method of PWR fuel assembly can significantly improve the calculation accuracy of the key physical parameters of the reactor core.
-
图 1 非均匀建模方法轴向建模示意图
Figure 1. Schematic Diagram of Heterogeneous Modeling Method Axial Modeling
图 2 非均匀建模方法径向建模示意图
Figure 2. Schematic Diagram of Heterogeneous Modeling Method Radial Modeling
图 3 均匀建模方法轴向建模示意图
Figure 3. Schematic Diagram of Homogenous Modeling Method Axial Modeling
图 4 均匀建模方法径向建模示意图
Figure 4. Schematic Diagram of Homogenous Modeling Method Radial Modeling
图 5 不同建模方法对堆芯临界硼浓度的影响
Figure 5. Influence of Different Modeling Methods on Critical Boron Concentration of Reactor Core
-
[1] 姚波,向文欣,王鹏,等. AFA3G LE燃料组件的结构特点和设计论证[J]. 核动力工程,2015, 36(S1): 40-43. [2] 杨晓东. AFA 3G及其它高性能燃料组件[J]. 原子能科学技术,2003, 37(S1): 15-20. [3] 陈军,周有新,李石磊,等. 跨间交混格架对EPR堆芯DNBR裕量的影响[J]. 原子能科学技术,2013, 47(2): 249-253. doi: 10.7538/yzk.2013.47.02.0249 [4] 段蓉, 于超, 林俊, 等. 燃料组件格架对堆芯核设计参数的影响分析[C]//第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议. 西安: 西安交通大学, 2020 [5] GIRIEUD P, DAUDIN L, GARAT C, et al. Science Version 2: the most recent capabilities of the Framatome 3-D nuclear code package[C]//Conference: 9. International Conference on Nuclear Engineering. Nice Acropolis, France: Societe Francaise d'Energie Nucleaire, 2001. [6] 万承辉, 李云召, 郑友琦, 等. 压水堆燃料管理软件Bamboo-C研发及工业确认[C]//第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议. 西安: 西安交通大学, 2020. [7] ZU T J, XU J L, TANG Y Q, et al. NECP-Atlas: a new nuclear data processing code[J]. Annals of Nuclear Energy, 2019, 123: 153-161. doi: 10.1016/j.anucene.2018.09.016 [8] LIU Z Y, HE Q M, ZU T J, et al. The pseudo-resonant-nuclide subgroup method based global-local self-shielding calculation scheme[J]. Journal of Nuclear Science and Technology, 2018, 55(2): 217-228. doi: 10.1080/00223131.2017.1394232 [9] TIAN C, ZHENG Y Q, LI Y Z, et al. Neutron transport study based on assembly modular ray tracing MOC method[J]. Nuclear Power Engineering, 2015, 36(3): 157-161. [10] 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 [11] SMITH K S. Assembly homogenization techniques for light water reactor analysis[J]. Progress in Nuclear Energy, 1986, 17(3): 303-335. doi: 10.1016/0149-1970(86)90035-1 [12] RHODES J, SMITH K, XU Z W. CASMO-5 energy release per fission mode[C]//CASMO5 - Advanced Lattice Physics Code for Light Water Reactors. Interlaken Switzerland, 2008. [13] DOWNAR T, XU Y, SEKER V. Theory manual for the PARCS kinetics core simulator module[R]. Michigan: University of Michigan, 2010. [14] JOO H G, YOON J I, BAEK S G. Multigroup pin power reconstruction with two-dimensional source expansion and corner flux discontinuity[J]. Annals of Nuclear Energy, 2009, 36(1): 85-97. doi: 10.1016/j.anucene.2008.10.003 [15] 吴宏春. 核反应堆物理[M]. 北京: 中国原子能出版社, 2014: 112-113. -
下载:
点击查看大图
计量
- 文章访问数: 277
- HTML全文浏览量: 52
- PDF下载量: 44
- 被引次数: 0
