...
首页> 外文期刊>Annals of nuclear energy >The Evaluation Of Rcs Depressurization To Prevent Core Melting In Pressure Tube Reactors (candu-type)
【24h】

The Evaluation Of Rcs Depressurization To Prevent Core Melting In Pressure Tube Reactors (candu-type)

机译:防止压力管反应器(坎杜型)堆芯熔化的RCS减压评估

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       

摘要

Pressure tube reactors, especially of the CANDU-type, have a low-pressure vessel calandria - under an internal pressure near atmospheric. The calandria vessel is immersed into the water contained inside a concrete structure - the calandria vault. In the case of accidents with the loss of normal core heat sinks, the moderator inside the calandria (heavy water) could become the ultimate heat sink. Accident analysis using a newly developed model (ASQR) strengthens the importance of the inside cooling of the fuel channels in order to prevent severe accidents. Even if implementing those methods related to moderator for eliminating the impairment of the outside cooling of fuel channels, these are not sufficient. The new model has been compared against the well-known in-reactor LOCA experiment - PBF - NRU.rnThus, the paper makes a review of author's article [Mehedinteanu, S., 2001. An application of the new way to prevent core melting in pressure tube reactors (CANDU-type). Annals of Nuclear Energy 28, 79-88] and describes a new method to prevent the core melting in the pressure tube reactors. The method concerns the use of a safety depressurization of the pressurizer (PDS) by means of a new safety valve block located on the line to the degasser-condenser (DC) and subsequent "re-pumping" of the water as collected in the DC, by the pressure difference intrinsically created, back to RCS through new lines connected with the emergency core cooling system (ECCS) lines. The result of the calculation shows a full prevention of the core melting in the pressure tube reactor (CANDU-type) and this conclusion could also be extended to LWR.
机译:压力管反应器,尤其是CANDU型压力管反应器,在接近大气压的内部压力下具有低压容器排管。排管容器浸入混凝土结构-排管室中的水中。在发生事故时,由于失去了正常的核心散热片,因此排管内部的减速器(大量水)可能成为最终的散热片。使用新开发的模型(ASQR)进行事故分析可增强燃料通道内部冷却的重要性,以防止发生严重事故。即使实施与缓和剂有关的那些方法以消除燃料通道的外部冷却的损害,这些还不够。将该新模型与著名的反应器内LOCA实验-PBF-NRU.rnTh进行了比较,本文对作者的文章进行了综述[Mehedinteanu,S.,2001。压力管反应器(CANDU型)。核能年鉴28,79-88]并描述了一种防止堆芯在压力管反应堆中熔化的新方法。该方法涉及通过位于通往脱气冷凝器(DC)的管线上的新安全阀块对增压器(PDS)进行安全降压,以及随后对DC中收集的水进行“重新泵送”通过固有的压力差,通过与应急堆芯冷却系统(ECCS)管线连接的新管线返回RCS。计算结果表明,可以完全防止压力管反应堆(CANDU型)堆芯熔化,该结论也可以推广到轻水堆。

著录项

  • 来源
    《Annals of nuclear energy》 |2009年第4期|537-545|共9页
  • 作者

    Stefan Mehedinteanu;

  • 作者单位

    CITON - Center of Technology and Engineering for Nuclear Projects, Sir. Atomistilor No. 409, BOP-5204-MC-4, Oras Magurele, Ilfov, Romania;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号