Preliminary Neutronics Analysis for Fluorine-Salt-Cooled Pebble-Bed Reactor

被引：0

作者：

Li Z. ^{[1
]}

Zhao C. ^{[1
]}

Zhang G. ^{[2
]}

Han S. ^{[1
]}

Huang J. ^{[1
]}

机构：

[1] China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen

[2] Science and Technology on Parallel and Distributed Processing Laboratory, National University of Defense Technology, Changsha

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷 / 02期

关键词：

Fuel pebble power; Group cross sections; Multiplication coefficient; Pebble-bed fluoride-salt-cooled high-temperature reactor; Random distribution;

D O I：

10.13832/j.jnpe.2021.02.0197

中图分类号：

学科分类号：

摘要：

In order to obtain the key neutronics parameters of the pebble-bed fluoride-salt-cooled high-temperature reactor (PB-FHR), the random packing method is used to obtain the coordinates of the three layers of isotropic coated particles (TRISO) particles, and the discrete element method is adopted to the coordinates of the fuel pebbles within the active core. Then the neutron transport calculated is conducted by the Monte Carlo code to analyze the effects of the fuel random distribution on the core neutronics parameters. The calculation results showed that the effects of the random distribution on the multiplication coefficient, group cross section and active core fuel pebble power can be neglected. Based on the above results, the nuclear design of the pebble-bed fluoride-salt-cooled high-temperature reactor can be simplified. © 2021, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：197 / 201

页数：4

共 19 条

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