期刊文献+

200 MW低温核供热堆非能动余热排出系统动态分析 被引量:4

Transient Analysis of Residual Heat Removal System Used in 200 MW Low Temperature Heating Reactor
下载PDF
导出
摘要 200 MW低温核供热堆的余热排出系统由3个耦合的自然循环回路组成。本文对该系统的热工水力特性进行了理论分析。在一维质量、动量和能量守恒方程的基础上建立了非能动余热排出系统的数学模型,并编制程序对模型进行了数值求解,模拟了非能动余热排出系统的瞬态特性。经验证,该系统的排热能力满足设计要求。 The residual heat removal system of 200 MW Heating Reactor is constituted by 3 coupled natural circulations. The thermal-hydraulic analysis numeric model of the passive residual heat removal equation, momentum equation and energy equation. model and simulate the heat removal process of the the system meet the design requirements. of the system has been performed in this paper, and the system has been constructed based on 1-demansion mass The program in this paper has been used to compute the system. The results show that the heat transfer ability of
作者 徐钊 吴莘馨
出处 《核动力工程》 EI CAS CSCD 北大核心 2008年第2期61-65,共5页 Nuclear Power Engineering
关键词 低温核供热堆 余热排出系统 动态分析 换热器 自然循环 Low t-emperature heat supply reactor, Residual heat removal system, Transient analysis,Heat exchanger, Natural circulation
  • 相关文献

参考文献4

二级参考文献3

共引文献4

同被引文献33

  • 1田嘉夫,赵兆颐,杨富,向勤,魏树炳,郭跃武.200MW深水池6型供热堆(DPR-6)的方案设计[J].核科学与工程,1995,15(3):199-206. 被引量:1
  • 2田嘉夫,赵兆颐,杨富,向勤,魏树炳.120MW池式低温供热堆[J].原子能科学技术,1995,29(1):33-40. 被引量:5
  • 3臧明昌.第三代核电和西屋公司AP1000评述[J].核科学与工程,2005,25(2):106-115. 被引量:36
  • 4沈瑾,江光明,唐钢,余红星.先进堆非能动余热排出系统应对全厂断电事故的能力分析[J].核动力工程,2007,28(2):87-90. 被引量:10
  • 5JUHN P E, KUPITZ J, CLEVELAND J, et al.IAEA activities on passive safety systems and overview of international development[J]. Nucle- ar Engineering and Design, 2000, 201: 42-59. 被引量:1
  • 6XU Y, ISHII M, FELTUS M A. Safety analysis of multiple-failure of passive safety systems in SBWR-1200 SBLOCA[J]. Nuclear Engineering and Design, 2004, 230: 107-119. 被引量:1
  • 7HART J, SLEGERS W J M, de BOER S L, et aL TEPSS-Technology enhancement for passive safety systems[J]. Nuclear Engineering and De- sign, 2001, 209: 243-252. 被引量:1
  • 8ANDRITSOS F, ANGELINI A, BARTELS H W, et al. SEAFP: Passive removal of the decay heat[J]. Fusion Engineering and Design, 1995, 29: 193-197. 被引量:1
  • 9CHUNGY J, YANG S H, KIM H C, et al. Thermal hydraulic calculation in a passive residu al heat removal system of the SMART-P plan for forced and natural convection eonditions[J]. Nuclear Engineering and Design, 2004, 232: 277-288. 被引量:1
  • 10SATO T, OIKAWA H, AKINAGA M, et al. Different variations of a passive safety contain- ment for a BWR with active and passive safety systems[J]. Nuclear Engineering and Design, 2005, 235:2 125-2 139. 被引量:1

引证文献4

二级引证文献7

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部