基于压水堆工况下CFETR水冷包层的增殖区破口事故初步分析

doi:10.3969/j.issn.0253-2778.2017.06.005

中国科学技术大学学报 ›› 2017, Vol. 47 ›› Issue (6): 479-484.DOI: 10.3969/j.issn.0253-2778.2017.06.005

基于压水堆工况下CFETR水冷包层的增殖区破口事故初步分析

杨枭，赵平辉，葛志浩，李远杰，聂星辰，刘佳明

中国科学技术大学核科学技术学院，安徽合肥 230022

收稿日期:2016-09-28 修回日期:2016-11-07 出版日期:2017-06-30 发布日期:2017-06-30
通讯作者: 赵平辉
作者简介:杨枭，男，1992年生，硕士.研究方向：聚变堆包层安全.E-mail：yang0520@mail.ustc.edu.cn
基金资助:
高校青年创新基金（WK2090130019）, 国家重点基础研究发展（973）计划（2103GB108004）资助.

Investigation into the In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions

YANG Xiao, GE Zhihao, LI Yuanjie, NIE Xingchen, LIU Jiaming

School of Nuclear Science and Technology，University of Science and Technology of China，Hefei 230022，China

Received:2016-09-28 Revised:2016-11-07 Online:2017-06-30 Published:2017-06-30

摘要/Abstract

摘要： 中国聚变工程实验堆（China Fusion Engineering Testing Reactor,CFETR）是一个类ITER的聚变实验堆.基于压水堆工况下的水冷包层是其包层设计的一种.使用RELAP5/MOD3.4对压水堆工况下的CFETR水冷包层做了增殖区破口事故的初步分析，详细描述了其事故进程并对事故结果做了简要分析.根据计算结果， CFETR水冷包层在事故中并没有发生面向等离子体第一壁熔化或氢气产量超过限值的情况.由于安全阀的存在，破口后冷却剂可以进入真空室.这使得包层的整体性得到了保障.此外由于真空室体积巨大，破口后其压力最终值也在安全阈值之下.

关键词: 中国聚变工程实验堆, 水冷包层, 压水堆工况, RELAP5/MOD3.4, 增殖区破口事故

Abstract: China Fusion Engineering Testing Reactor（CFETR）is an “ITER-like” DEMO fusion reactor in China. As one of the breeding blanket candidates for CFETR, a water cooled breeder blanket based on PWR conditions has been designed. Here In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions was investigated by RELAP5/MOD3.4. The accident’s processes were described in detail and its results were analyzed preliminarily.According to the computational results, first wall (FW) does not melt and the production of hydrogen is lower than the limit. Meanwhile, due to the rupture disk, the flow can vent into the vacuum vessel(VV) after the accident, which ensures the integrity of the blanket. And due to the large volume of the VV, the final pressure of VV is much lower than the limit.

Key words: CFETR;water cooled solid breeder blanket, PWR condition, RELAP5/MOD3.4, In-box LOCA

中图分类号:

TL62

杨枭，赵平辉，葛志浩，李远杰，聂星辰，刘佳明. 基于压水堆工况下CFETR水冷包层的增殖区破口事故初步分析[J]. 中国科学技术大学学报, 2017, 47(6): 479-484.

YANG Xiao, GE Zhihao, LI Yuanjie, NIE Xingchen, LIU Jiaming. Investigation into the In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions[J]. Journal of University of Science and Technology of China, 2017, 47(6): 479-484.

参考文献

［1］
LI J G.Closing gaps to CFETR readiness[C]// IAEA TCM 3rd DEMO Workshop, Hefei, China. 2015: 11-14.

[2] LIU S, PU Y, CHENG X, et al. Conceptual design of a water cooled breeder blanket for CFETR[J]. Fusion Engineering and Design, 2014, 89(7): 1380-1385.

[3] AHN M Y, CHO S, KIM D H, et al. Preliminary safety analysis of Korea helium cooled solid breeder test blanket module[J]. Fusion Engineering and Design, 2008, 83(10): 1753-1758.

[4] LEE D W, JIN H G, SHIN K I, et al. Investigation into the In-box LOCA consequence and structural integrity of the KO HCCR TBM in ITER[J]. Fusion Engineering and Design, 2014, 89(7): 1177-1180.

[5] JIN H G, LEE D W, LEE E H, et al. Sensitivity study on In-box LOCA for a Korean HCCR TBM in ITER[J]. Fusion Engineering and Design, 2014, 89(9): 2024-2027.

[6] BOCCACCINI L V, CIATTAGLIA S, MEYDER R, et al. Review of accidental safety studies for the European HCPB test blanket system[J]. Nuclear fusion, 2007, 47(7): S436.

[7] 李伟, 田文喜, 秋穗正, 等. 基于 RELAP5 的双功能液态锂铅实验包层模块安全分析[J]. 原子能科学技术, 2013, 47(11): 2046-2052.
LI Wei, TIAN Wenxi, QIU Suizheng, et al. Safety analysis on dual-functional lithium lead test blanket module with RELAP5[J]. Atomic Energy Science and Technology, 2013, 47(11): 2046-2052.

[8] WANG J, TIAN W, SU G, et al. Thermal-hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system[J]. Fusion Engineering and Design, 2013, 88(1): 33-41.

[9] AHN M Y, CHO S, KU D Y, et al. LOCA analysis for Korean helium cooled solid breeder TBM[J]. Fusion Engineering and Design, 2009, 84(2): 380-384.

[10] WANG S, ZHOU G, LV Z, et al. Design and safety analysis of the helium cooled solid breeder blanket for CFETR[J]. Kerntechnik, 2016, 81(2): 192-196.

[11] AHN M Y, JIN H G, CHO S, et al. Current status of accident analysis for Korean HCCR TBS[J]. Fusion Engineering and Design, 2014, 89(7): 1289-1293.

[12] JIN X, BOCCACCINI L V, MEYDER R. Deterministic safety analysis of the reference accidental sequence for the European HCPB TBM system[J]. Fusion Engineering and Design, 2008, 83(10): 1759-1763.

[13] ANDERL R A, MCCARTHY K A, OATES M A, et al. Steam-chemical reactivity for irradiated beryllium[J]. Journal of Nuclear Materials, 1998, 258: 750-756.

[14] ANDERL R A, SCAFFIDI-ARGENTINA F, DAVYDOV D, et al. Steam chemical reactivity of Be pebbles and Be powder[J]. Journal of Nuclear Materials, 2000, 283: 1463-1467.

[15] JIN X Z, MERRILL B J, BOCCACCINI L V. Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system[J]. Fusion Engineering and Design, 2012, 87(5): 454-460.

基于压水堆工况下CFETR水冷包层的增殖区破口事故初步分析

Investigation into the In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions

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