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Method for the evaluation by simulation of leaks from nuclear reactor vessel cover crossings in operation during a shutdown.

机译:通过模拟停机期间运行中的核反应堆容器盖交叉口泄漏的评估方法。

摘要

A mixt. of tracer gases (43) contg. helium is injected into the chamber (7) where any leaks (10) from penetrations through the reactor head would emerge. A mass spectrometer (45) is placed in a double sampling circuit (12-15, 100,16,17) to detect and measure the concn. of the tracer gas in samples extracted from inside the chamber (7) and, as a reference, from inside the reactor building (100). USE/ADVANTAGE - To determine the flow rate inside the chamber (7) and to verify the sampling system, during shutdown. Sensitive measurement since the sample is taken before the tracer gas is diluted by the air flow cooling the control rod drive mechanisms (3).
机译:混蛋示踪气体(43)续。将氦气注入腔室(7),在该腔室中会出现通过反应器顶部穿透而引起的任何泄漏(10)。将质谱仪(45)置于双采样电路(12-15、100、16、17)中,以检测和测量浓度。从腔室(7)内部以及作为参考从反应堆建筑物(100)内部提取的样品中的示踪气体的含量。使用/优点-在关闭期间,确定腔室内(7)的流速并验证采样系统。灵敏的测量,因为在冷却控制杆驱动机构(3)的气流稀释示踪气体之前采集了样品。

著录项

  • 公开/公告号FR2697940B1

    专利类型

  • 公开/公告日1997-10-17

    原文格式PDF

  • 申请/专利权人 ELECTRICITE DE FRANCE;

    申请/专利号FR19930004464

  • 发明设计人 LOISY FRANCOIS;GERMAIN JEAN-LUC;

    申请日1993-04-15

  • 分类号G21C13/036;G21C17/003;G01M3/20;

  • 国家 FR

  • 入库时间 2022-08-22 03:12:32

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