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International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)

机译:国际标准问题和小型休闲丧失冷却液事故(SBLOCA)

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摘要

Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test facilities. OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) has promoted, over the last twenty-nine years, some forty-eight international standard problems (ISPs). These ISPs were performed in different fields as in-vessel thermal-hydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermal-hydraulic behaviour. 80% of these ISPs were related to the working domain of principal working group no.2 on coolant system behaviour (PWG2) and were one of the major PWG2 activities for many years. A global review and synthesis on the contribution that ISPs have made to address nuclear reactor safety issues was initiated by CSNI-PWG2 and an overview on the subject of small break LOCA ISPs is given in this paper based on a report prepared by a writing group. In addition, the relevance of small break LOCA in a PWR with relation to nuclear reactor safety and the reorientation of the reactor safety program after TMI-2 accident are shortly summarized. The experiments in four integral test facilities, LOBI, SPES, BETHSY, ROSA IV/LSTF and the recorded data during a steam generator tube rupture transient in the DOEL-2 PWR (Belgium) were the basis of the five small break LOCA related ISP exercises, which deal with the phenomenon typical of small break LOCAs in Western design PWRs. Some lessons learned from these small break LOCA ISPs are identified in relation to code deficiencies and capabilities, progress in the code capabilities, possibility of scaling, and various additional aspects. ISPs are providing unique material and benefits for some safety-related issues.
机译:最佳估计热工水力系统代码被广泛用于执行安全和核电厂的许可的分析和提前反应器的设计也有使用。的能力和这些码的性能的评价可以通过比较代码预测具有在不同的测试设施得到的测量的实验数据来完成。 OECD / NEA委员会有关核设施安全(CSNI)推动,在过去的29年,一些48国际标准问题(互联网服务提供商)。这些ISP分别在不同的领域如在船热工水力行为,事故条件下的燃料的行为,裂变产物释放和输送,芯/混凝土相互作用,氢键分布和混合,遏制热工水力行为执行。这些ISP的80%涉及到对冷却系统的行为主要工作组第2号(PWG2)的工作领域和分别多年的主要PWG2活动之一。对互联网服务供应商不得不被CSNI-PWG2和小破口事故的ISP的主题概述发起地址核反应堆安全问题所作出的贡献的全球审查​​和合成本文基于由编写组编写的一份报告中给出。此外,小破口LOCA与有关核反应堆安全和反应堆安全程序的TMI-2事故发生后的重新定位压水堆的相关性都很快总结。在DOEL-2 PWR(比利时)的蒸汽发生器管破裂瞬态期间在四个整体测试设施,LOBI,SPES,BETHSY,ROSA IV / L-STF和所记录的数据的实验是五个小破LOCA相关ISP练习的基础,该处理的现象典型的西方设计的压水堆小破口的LOCA。从这些小破口事故互联网服务供应商吸取了一些经验教训有关的代码缺陷和能力,在编码功能的进步,缩放的可能性,以及各种其他方面的鉴定。互联网服务供应商对某些与安全相关的问题提供独特的材料和福利。

著录项

  • 作者

    N. Aksan;

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  • 年度 2008
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  • 原文格式 PDF
  • 正文语种 eng
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