Double heterogeneity effect analysis for plate fuel with dispersed particles

被引:1
作者
Yuan, Anmin [1 ]
Wu, Hongchun [1 ]
Li, Yunzhao [1 ,2 ]
Cao, Liangzhi [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian, Peoples R China
[2] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, 28 Xianning West Rd, Xian 710049, Shaanxi, Peoples R China
关键词
Plate fuel with dispersed fuel particles; Dispersed burnable poison particles; Double heterogeneity; NECP-MCX; GEOMETRY CAPABILITY; CODE;
D O I
10.1016/j.anucene.2023.109894
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In order to identify the strong double heterogeneity (DH) effect of dispersed particle fuel with plate type, a suit of problems with 63 cases have been defined and analyzed by using the Monte Carlo code NECP-MCX. Numerical results indicate the following findings. (1) For cases with only fuel particles, the DH effect is within 50 pcm when the diameters are below 300 mu m. (2) For cases with both fuel and burnable poison particles, eigenvalue deviation between the random dispersion case and the homogenized case can reach up to the maximum of 905 pcm. Even if, the diameter of burnable poison particles is very small (20 mu m), the deviation is more than 150 pcm, making the homogenization approach no longer applicable. This work provides a data basis for correcting neutronic calculations and can be used as reference for verifying the calculation program based on the new method.
引用
收藏
页数:13
相关论文
共 64 条
[1]   Neutron diffusion coefficient for disordered arrays of TRISO particles in spherical nuclear fuel [J].
Aguilar-Madera, C. G. ;
Herrera-Hernandez, E. C. ;
Espinosa-Paredes, G. .
ANNALS OF NUCLEAR ENERGY, 2020, 146
[2]   Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor [J].
Alameri, Saeed A. ;
Alrwashdeh, Mohammad .
ANNALS OF NUCLEAR ENERGY, 2021, 163
[3]   Stochastic geometry capability in MCNP5 for the analysis of particle fuel [J].
Brown, FB ;
Martin, WR .
ANNALS OF NUCLEAR ENERGY, 2004, 31 (17) :2039-2047
[4]   High volume packing fraction TRISO-based fuel in light water reactors [J].
Brown, Nicholas R. ;
Hernandez, Richard ;
Nelson, Andrew T. .
PROGRESS IN NUCLEAR ENERGY, 2022, 146
[5]   A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications [J].
Brown, Nicholas R. .
JOURNAL OF NUCLEAR MATERIALS, 2020, 534
[6]   Postirradiation examinations of low burnup U3Si2 fuel for light water reactor applications [J].
Cappia, Fabiola ;
Harp, Jason M. .
JOURNAL OF NUCLEAR MATERIALS, 2019, 518 :62-79
[7]  
[陈珍平 Chen Zhenping], 2020, [核动力工程, Nuclear Power Engineering], V41, P62
[8]  
Donovan T., 2003, HTGR UNIT FUEL PEBBL
[9]   Current status of materials development of nuclear fuel cladding tubes for light water reactors [J].
Duan, Zhengang ;
Yang, Huilong ;
Satoh, Yuhki ;
Murakami, Kenta ;
Kano, Sho ;
Zhao, Zishou ;
Shen, Jingjie ;
Abe, Hiroaki .
NUCLEAR ENGINEERING AND DESIGN, 2017, 316 :131-150
[10]  
Feng H., 2019, CHINA NUCL POWER, V12, P566