欢迎访问《核聚变与等离子体物理》官方网站,今天是 分享到:

核聚变与等离子体物理 ›› 2013, Vol. 33 ›› Issue (2): 175-180.

• 核聚变工程技术 • 上一篇    下一篇

ITER 第一壁冷却剂管道断裂事故热工水力初步分析

李若晴,佟立丽,曹学武   

  1. (上海交通大学机械与动力工程学院,上海 200240)
  • 收稿日期:2012-10-26 修回日期:2013-03-20 出版日期:2013-06-15 发布日期:2013-06-14
  • 作者简介:李若晴(1989-),男,山东省德州市人,硕士研究生,核能科学与工程专业。
  • 基金资助:

    国际热核聚变实验反应堆(ITER)计划专项(2010GB109004,2013GB114005),国家自然科学基金(11205099)

Preliminary analysis of the thermal-hydraulic behavior induced by first wall coolant pipe leakage accidents for ITER

LI Ruo-qing, TONG Li-li, CAO Xue-wu   

  1. (School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240)
  • Received:2012-10-26 Revised:2013-03-20 Online:2013-06-15 Published:2013-06-14

摘要:

采用一体化安全分析程序,建立了ITER 装置第一壁/包层及其主热传输系统、抑压系统的事故分析模型。对真空室内第一壁冷却剂管道双端断裂的失水事故进行计算,并选取单根冷却剂管道双端断裂和多根冷却剂管道双端断裂导致的失水事故工况进行热工水力行为的研究,分析相关系统的热力响应。分析表明,在发生第一壁冷却剂管道断裂事故后,由于冷却剂向真空室内释放,导致真空室内压力升高,之后由于抑压系统爆破盘的开启,可以有效缓解真空室内压力的升高,能够保障真空室系统满足设计限值。

关键词: ITER, 聚变堆安全, 真空室, 失水事故, 管道断裂

Abstract:

Using an integral safety analysis code, an accident analysis model for the vacuum vessel (VV), first wall (FW)/blanket, its primary heat transfer system and the pressure suppression system of ITER is built. The loss of coolant accident induced by the in-vessel first wall pipe double-ended rupture is selected with two different cases of single pipe rupture and multiple pipe rupture as the initial scenarios to investigate the thermal-hydraulic responses for the systems. For the accidents of in-vessel FW coolant pipe double-ended rupture, the pressure in VV increases with the coolant releasing, and then decreases with the rupture disk opening, which shows that the pressure in VV remains in the design limitation.

Key words: ITER, Fusion safety, In-vessel, Loss of coolant accident, Pipe rupture

中图分类号: