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某核电堆型蒸汽发生器排污系统设计改进 被引量:5

Design Improvement of Steam Generator Blowdown System
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摘要 根据全范围事故分析结果,在发生蒸汽发生器传热管破裂(SGTR)事故中,为使发生故障的蒸汽发生器水位不会上升太快,需通过蒸汽发生器排污系统排污管线来控制故障蒸发器的水位和压力。通过对蒸汽发生器排污系统进行设计改进,提高系统的设计标准,将破损蒸汽发生器内漏液排向内置换料水箱,使破损蒸汽发生器降压,同时限制破损蒸汽发生器水位,防止破损蒸汽发生器满溢,满足蒸汽发生器排污系统在设计基准事故工况下承担安全功能的要求。改进后的蒸汽发生器排污系统满足国内三代核电技术的要求,为国内三代核电的安全性提供理论依据。 According to the results of the full range of accident analysis, in case of steam generator tube rupture, in order to make affected SG water level will not rise too fast, and need to control the affected SG water level and pressure by steam generator blowdown system. According to design improvement of steam generator blowdown system, increase the system design bases, the blowdowns are routed to the IRWST inside the containment, in order to depressurize affected SG pressure and control affected SG level, to prevent the affected steam generator is filled with water, meet the requirements of steam generator blowdown system in the design basis accident under the safety function. The improvement design can satisfy the third generation nuclear power technology, provide theoretical basis for the safety of the third generation nuclear power in China.
出处 《南方能源建设》 2016年第3期45-47,53,共4页 Southern Energy Construction
关键词 蒸汽发生器排污 安全功能 传热管破裂事故 steam generator blowdown safety function SGTR
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参考文献3

  • 1中国核电工程有限公司. 蒸汽发生器排污系统手册(CP03XTTBXTS02) [M] . 北京:CNPE,2015.
  • 2中国核电工程有限公司.运行技术规范(O426XOTSYXBO3 )[M] .北京:CNPE,2011.
  • 3张往锁,曹夏昕,曹建华.非能动余热排出系统敏感性分析[J].原子能科学技术,2013,47(3):409-415. 被引量:2

二级参考文献14

  • 1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
  • 2JUHN 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.
  • 3XU 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.
  • 4HART 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.
  • 5ANDRITSOS F, ANGELINI A, BARTELS H W, et al. SEAFP: Passive removal of the decay heat[J]. Fusion Engineering and Design, 1995, 29: 193-197.
  • 6CHUNGY 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.
  • 7SATO 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.
  • 8XIAO Zejun, ZHUO Wenbin, ZHENG Hua, et al. Experimental research progress on passive safety systems of Chinese advanced PWR [J]. Nuclear Engineering and Design, 2003, 225: 305-313.
  • 9沈瑾,江光明,唐钢,余红星.一体化先进堆全厂断电事故下非能动余热排出系统能力分析[J].核动力工程,2007,28(6):80-83. 被引量:6
  • 10徐钊,吴莘馨.200 MW低温核供热堆非能动余热排出系统动态分析[J].核动力工程,2008,29(2):61-65. 被引量:4

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