Fuel Management Code Development and Analysis for Pebble Bed-fluoride Salt-cooled High Temperature Reactor

被引：0

作者：

Jia G. ^{[1
,2
,3
]}

Dai Y. ^{[1
,2
]}

Wu J. ^{[1
,2
]}

Chen J. ^{[1
,2
,3
]}

Gu G. ^{[1
,2
]}

Cai X. ^{[1
,2
,3
]}

机构：

[1] Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai

[2] CAS Innovative Academies in TMSR Energy System, Shanghai

[3] University of Chinese Academy of Sciences, Beijing

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2021年 / 55卷 / 02期

关键词：

Fuel management; Homogenization; PBMSR code; Pebble bed-fluoride salt-cooled high temperature reactor;

D O I：

10.7538/yzk.2020.youxian.0135

中图分类号：

TL4 [各种核反应堆、核电厂];

学科分类号：

082703 ;

摘要：

There are three challenges needed to be solved in pebble bed-fluoride salt-cooled high temperature reactor (PB-FHR) by using the deterministic neutron analysis codes, which are homogenization of double heterogeneity fuel pebble, leakage effect during homogenization and the continuous movement of fuel pebble in the core and multi-pass fuel management mode. Based on DRAGON5 and DONJON5 codes, a PB-FHR fuel management code PBMSR was developed and verified. PBMSR was used to calculate the PB-FHR with different fuel cycle modes. The results show that the number of a fuel pebble passing the core has little impact on the optimal discharged burnup in the multi-pass fuel cycle mode, but has great impact on the axial power distribution. © 2021, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：286 / 295

页数：9

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