留言板

尊敬的读者、作者、审稿人, 关于本刊的投稿、审稿、编辑和出版的任何问题, 您可以本页添加留言。我们将尽快给您答复。谢谢您的支持!

姓名
邮箱
手机号码
标题
留言内容
验证码

高增益包层失流事故热工安全分析

戴涛 黄洪文 马纪敏 丁文杰 郭海兵 王少华

戴涛, 黄洪文, 马纪敏, 等. 高增益包层失流事故热工安全分析[J]. 强激光与粒子束, 2019, 31: 036001. doi: 10.11884/HPLPB201931.180284
引用本文: 戴涛, 黄洪文, 马纪敏, 等. 高增益包层失流事故热工安全分析[J]. 强激光与粒子束, 2019, 31: 036001. doi: 10.11884/HPLPB201931.180284
Dai Tao, Huang Hongwen, Ma Jimin, et al. Thermal safety analysis on high tritium breeding blanket for loss of flow accident[J]. High Power Laser and Particle Beams, 2019, 31: 036001. doi: 10.11884/HPLPB201931.180284
Citation: Dai Tao, Huang Hongwen, Ma Jimin, et al. Thermal safety analysis on high tritium breeding blanket for loss of flow accident[J]. High Power Laser and Particle Beams, 2019, 31: 036001. doi: 10.11884/HPLPB201931.180284

高增益包层失流事故热工安全分析

doi: 10.11884/HPLPB201931.180284
基金项目: 

国家磁约束核聚变能发展研究专项 2015GB108003

详细信息
    作者简介:

    戴涛(1994—), 男,硕士研究生,从事反应堆热工水力及安全分析研究;dai_tao@outlook.com

    通讯作者:

    黄洪文(1975—), 男,研究员,从事反应堆热工水力相关研究;hhw@caep.cn

  • 中图分类号: TL36

Thermal safety analysis on high tritium breeding blanket for loss of flow accident

  • 摘要: 利用系统分析程序RELAP5/Mod 3.4对基于中国聚变工程实验堆(CFETR)的高增益包层聚变堆进行了全堆尺度的安全分析。针对包层结构复杂、部件众多的特点,提出了对包层两套冷却系统的复杂流动和传热结构的等效建模方法,并建立了两套冷却系统间的传热模型。在此基础上完成全包层模型,对稳态运行工况进行了计算验证,并选取燃料区全部失流事故进行安全分析。计算结果表明:在事故过程中,第一壁-产氚区冷却系统能够带走燃料区的部分衰变热,高增益包层的各项热工参数均未超过限值。这表明包层能够有效地抵御此类事故,具有良好的热工安全特性。
  • 图  1  高增益包层结构设计

    Figure  1.  Structure design of high tritium breeding blanket (HTBB)

    图  2  1/4包层截面图

    Figure  2.  1/4 blanket cross section

    图  3  子模块中的第一壁-产氚区和燃料区冷却回路

    Figure  3.  FW-tritium breeder pebble beds and fuel zone cooling loops in a sub-module

    图  4  两种燃料区冷却流道模型

    Figure  4.  Two kinds of fuel zone cooling loop models

    图  5  第一壁-产氚区冷却流道模型

    Figure  5.  FW-tritium breeder pebble beds cooling pipe model

    图  6  第一壁热构件结构

    Figure  6.  Heat structure of the first wall(FW)

    图  7  燃料区热构件

    Figure  7.  Heat structures of the fuel zone

    图  8  高增益包层聚变堆节点图

    Figure  8.  RELAP nodalization for the HTBB blanket fusion reactor

    图  9  燃料区回路冷却剂质量流量

    Figure  9.  Mass flow of coolant of the fuel zone loop

    图  10  燃料区回路系统压力

    Figure  10.  System pressure of the fuel zone loop

    图  11  燃料区进出口冷却剂温度

    Figure  11.  Coolant temperature at the inlet and outlet of the fuel zone

    图  12  第一壁-产氚区进出口冷却剂温度

    Figure  12.  Coolant temperature at the inlet and outlet of the FW-tritium breeder zone

    图  13  燃料最高温度

    Figure  13.  Maximum temperature of the fuel

    图  14  最小偏离核态沸腾比

    Figure  14.  Minimum departure from nucleate boiling ratio(MDNBR)

    表  1  RELAP5与主要热工水力参数设计值对比

    Table  1.   Main thermal-hydraulic parameters comparison of RELAP5 results and design values

    parameter coolant temperatures at the inlet/outlet of the FW-tritium breeding zone cooling system/℃ coolant temperatures at the inlet/outlet of the fuel zone cooling system/℃ coolant mass flow of the FW-tritium breeding zone cooling system /(kg·s-1)
    RELAP5 279.65/319.41 279.84/319.26 959.68
    designed value 280/320 280/320 961.71
    parameter coolant mass flow of the fuel zone cooling system/(kg·s-1) pressure of the FW-tritium breeding zone cooling system/MPa pressure of the fuel zone cooling system/MPa
    RELAP5 3 302.50 15.50 15.50
    Designed value 3 302.94 15.50 15.50
    下载: 导出CSV

    表  2  改变热构件后主要热工水力参数

    Table  2.   Main thermal-hydraulic parameters after heat structures changed

    parameter coolant temperatures at the inlet/outlet of the FW-tritium breeding zone cooling system/℃ coolant temperatures at the inlet/outlet of the fuel zone cooling system/℃ coolant mass flow of the FW-tritium breeding zone cooling system /(kg·s-1)
    RELAP5 280.35/326.62 279.35/316.85 959.68
    parameters coolant mass flow of the fuel zone cooling system/(kg·s-1) pressure of the FW-tritium breeding zone cooling system/MPa pressure of the fuel zone cooling system/MPa
    RELAP5 3 302.50 15.72 15.47
    下载: 导出CSV

    表  3  全部主泵失电事件序列

    Table  3.   Sequence of all main pumps lose efficacy

    event time/s
    main pumps loss of off-site power supply 100.00
    plasma shutdown 100.77
    Minimum departure from nucleate boiling ratio(MDNBR) reaches the minimum value 102.00
    system pressure reaches the maximum value 138.00
    coolant temperature reaches the peak value 142.00
    下载: 导出CSV
  • [1] Song Y T, Wu S T, Li J G, et al. Conceptual design of CFETR tokamak machine[J]. IEEE Transactions on Plasma Science, 2014, 42(3): 503-509. doi: 10.1109/TPS.2014.2299277
    [2] Liu Songlin, Ma Xuebin, Jiang Kecheng, et al. Conceptual design of the water cooled ceramic breeder blanket for CFETR on pressurized water cooled reactor technology[J]. Fusion Engineering and Design, 2017, 124: 865-870. doi: 10.1016/j.fusengdes.2017.02.065
    [3] Chen Hongli, Li Min, Lü Zhongliang, et al. Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR[J]. Fusion Engineering and Design, 2015, 96/97: 89-94. doi: 10.1016/j.fusengdes.2015.02.045
    [4] Ni Muyi, Lian Chao, Zhang Shichao, et al. Structural design and preliminary analysis of liquid lead-lithium blanket for China Fusion Engineering Test Reactor[J]. Fusion Engineering and Design, 2015, 94: 61-66. doi: 10.1016/j.fusengdes.2015.03.018
    [5] 王少华, 郭海兵, 马纪敏, 等. 高氚增殖比包层的设计及热工水力分析[J]. 原子能科学技术, 2017, 51(12): 2125-2131. doi: 10.7538/yzk.2017.51.12.2125

    Wang Shaohua, Guo Haibing, Ma Jimin, et al. The design and thermal-hydraulic analysis of high tritium breeding blanket. Atom Energy Science and Technology, 2017, 51(12): 2125-2131 doi: 10.7538/yzk.2017.51.12.2125
    [6] 杨枭, 赵平辉, 葛志浩, 等. 基于压水堆工况的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. doi: 10.3969/j.issn.0253-2778.2017.06.005

    Yang Xiao, Zhao Pinghui, Ge Zhihao, et al. 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 doi: 10.3969/j.issn.0253-2778.2017.06.005
    [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. doi: 10.7538/yzk.2013.47.11.2046

    Li Wei, Tian Wenxi, Qiu Suizheng, et al. Safety analysis on dual-functional lithium lead test blanket module with RELAP5. Atom Energy Science and Technology, 2013, 47(11): 2046-2052 doi: 10.7538/yzk.2013.47.11.2046
    [8] 汪健, 宋云涛, 雷明准, 等. 基于RELAP5的CFETR氦冷陶瓷增值包层模块热工安全分析[J]. 原子能科学技术, 2017, 51(10): 1778-1784. doi: 10.7538/yzk.2017.51.10.1778

    Wang Jian, Song Yuntao, Lei Mingzhun, et al. Thermal safety analysis of CFETR helium cooled ceramic breeder blanket module with RELAP5. Atom Energy Science and Technology, 2017, 51(10): 1778-1784 doi: 10.7538/yzk.2017.51.10.1778
    [9] The RELAP5 Development Team. RELAP5/MOD3 code manual, volumeⅤ: User's guidelines, NUREG/CT-5535[M]. US: Idaho National Laboratory, 2001.
    [10] 俞冀阳, 俞尔俊. 核电厂事故分析[M]. 北京: 清华大学出版社, 2012.

    Yu Jiyang, Yu Eejun. Accident analysis of nuelear power ploant. Beijing: Tsinghua University Press, 2012
  • 加载中
图(14) / 表(3)
计量
  • 文章访问数:  930
  • HTML全文浏览量:  261
  • PDF下载量:  74
  • 被引次数: 0
出版历程
  • 收稿日期:  2018-10-23
  • 修回日期:  2019-01-21
  • 刊出日期:  2019-03-15

目录

    /

    返回文章
    返回