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RE-EVALUATION OF PAR CONCEPT IN GERMAN PWR WITH REVISED PAR MODEL

机译:修正后的PAR模型对德国压水堆中PAR概念的重新评估

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Consideration and analysis of Beyond Design Basis Accidents (BDBA) and Severe Accident (SA) of NPPs is an essential component of the defence-in-depth approach used in nuclear safety. A set of Severe Accident Management (SAM) measures and guidelines is today applied to existing NPPs to be taken to prevent the SA or to mitigate its consequences. A basic concept for hydrogen mitigation inside the PWR containment of German plants by a large number of Passive Autocatalytic Recombiners (PAR) has been examined by GRS within the frame of projects sponsored by the German Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB) already in a period up to 2001. The PAR concepts have been realized in all German PWRs thereafter, while a re-evaluation of the concept was done at GRS more recently. Based on PSA level 2 results additional accident scenarios have been considered within the re-evaluation process. The GRS code COCOSYS has been applied again for the analyses with an updated input deck including the latest code models available, especially the new PAR model. Within recently finished OECD/NEA THAI projects several new tests related to hydrogen recombination using different PAR types (Areva, AECL, NIS) have been performed, which allowed a significant improvement of the PAR models used in COCOSYS and other codes, including CFD codes. The COCOSYS calculations were conducted according to the state-of-the-art of me computer code as well as based on experiences gained in the meantime of the validations on experiments. The analyses results for the German PWR underlined the efficiency of the implemented PAR concept even under more challenging severe accident conditions; still local hydrogen combustion processes could not be avoided in all cases and were analyzed with COCOSYS for the first time. Various ignition criteria were applied, like a presumed ignition of the gas mixture by a PAR to determine the most challenging conditions (worst case) with regard to the combustion process and the resulting pressure peak. A summary of the results of the re-evaluation of the PAR concept for a German PWR is presented together with recommendations on appropriate code application for the development of PAR concepts in large dry, multi-compartment PWR containments. Further reference is made to a recently published OECD/NEA SOAR report on "Hydrogen Management and Related Computer Codes" in which the German regulatory requirements related to hydrogen mitigation are summarized.
机译:核电厂超越设计基础事故(BDBA)和严重事故(SA)的考虑和分析是核安全中使用的纵深防御方法的重要组成部分。今天,将一套严重事故管理(SAM)措施和指南应用于现有的NPP,以防止SA或减轻其后果。 GRS在德国联邦环境,自然保护,建筑和核能部资助的项目框架内,研究了由大量被动自催化重组器(PAR)缓解德国工厂压水堆内氢减氢的基本概念。安全性(BMUB)的使用期限一直到2001年。此后,所有德国压水堆都实现了PAR概念,而最近在GRS对该概念进行了重新评估。基于PSA 2级结果,在重新评估过程中还考虑了其​​他事故场景。 GRS代码COCOSYS已通过更新的输入平台再次应用于分析,其中包括最新可用的代码模型,尤其是新的PAR模型。在最近完成的OECD / NEA THAI项目中,已经进行了几个有关使用不同PAR类型(Areva,AECL,NIS)的氢重组相关的新测试,从而大大改善了COCOSYS和其他代码(包括CFD代码)中使用的PAR模型。 COCOSYS计算是根据最新的计算机代码以及在进行实验验证的同时获得的经验进行的。德国压水堆的分析结果强调了即使在更具挑战性的严重事故情况下,已实施的PAR概念的效率。仍然无法避免所有情况下的局部氢气燃烧过程,因此首次使用COCOSYS进行了分析。应用了各种点火标准,例如PAR推测的混合气体点火,以确定关于燃烧过程和最终压力峰值的最具挑战性的条件(最坏的情况)。介绍了对德国PWR的PAR概念进行重新评估的结果的摘要,以及有关在大型干燥,多隔间PWR密闭环境中开发PAR概念的适当代码应用的建议。进一步参考最近发布的关于“氢气管理和相关计算机代码”的OECD / NEA SOAR报告,其中总结了与缓解氢气有关的德国法规要求。

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