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Thermal limit analysis with hot-channel model for boiling water reactors

机译:热通道模型对沸水反应堆的热极限分析

摘要

An analytical method for the initial flux and transient hot water flow parameters for a boiling water reactor with single fuel bundle. Firstly, the method is to calculate intial flux and transient hot water flow parameter based on single fuel bundle. Then, it uses supplier provided CPR (Critical Power Ratio) correlation to calculate transient CPR and calculate the whole reactor core for hot water parameters as boundary condition. Iteration is used to figure out DCPR (Delta Critical Power Ratio). The obtained limit transient is selected as the maximum from DCPR. The maximum transient DCPR combines Safety Limit Minimum Critical Power Ratio (SLMCPR) and safety margin to figure out the OLMCPR (Operating Limit Minimum Critical Power Ratio). Both the plant layout and operational thermal limit are based on OLMCPR to assure the safety of reactor core.
机译:单燃料束沸水反应堆初始通量和瞬态热水流量参数的分析方法。首先,该方法是基于单个燃料束计算初始通量和瞬态热水流量参数。然后,它使用供应商提供的CPR(临界功率比)相关性来计算瞬态CPR并计算整个反应堆堆芯的热水参数作为边界条件。迭代用于计算DCPR(增量临界功率比)。从DCPR中选择获得的极限瞬变作为最大值。最大瞬态DCPR结合了安全极限最小临界功率比(SLMCPR)和安全裕度,以得出OLMCPR(工作极限最小临界功率比)。工厂布局和运行热极限均基于OLMCPR,以确保反应堆堆芯的安全。

著录项

  • 公开/公告号US2009168946A1

    专利类型

  • 公开/公告日2009-07-02

    原文格式PDF

  • 申请/专利权人 YANG-KAI CHIU;

    申请/专利号US20080968196

  • 发明设计人 YANG-KAI CHIU;

    申请日2008-01-02

  • 分类号G21C17/108;

  • 国家 US

  • 入库时间 2022-08-21 19:34:46

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