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首页> 外文期刊>Nuclear Engineering and Design >An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part Ⅰ: SETs, and ITFs of PWRs, BWRs, VVERs
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An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part Ⅰ: SETs, and ITFs of PWRs, BWRs, VVERs

机译：水冷核反应堆热工现象概述；

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摘要

Validation of best-estimate thermal-hydraulic system codes is a necessary step to prove their applicability to calculate nuclear plant accident scenarios, including the course of events. It shall demonstrate that those physical thermal-hydraulic phenomena, which are important for a nuclear plant transient and accident scenarios, are calculated and analysed appropriately for the design and safety analysis purposes. Within the framework of international organizations, e. g., the Committee on the Safety of Nuclear Installations of Nuclear Energy Agency of The Organization for Economic Cooperation and Development (OECD/NEA-CSNI) and the International Atomic Energy Agency (IAEA), with the major support of institutions from different countries, work has been carried out for establishing validation matrices on Separate Effects Test (SET) facilities and Integral Test facilities of PWRs and BWRs. During this process, one of the major elements of the activity was to identify and characterize the thermal-hydraulic phenomena and, also test types. This process was based on expert knowledge of the scientists involved and, approved by the participating organizations and institutions in different countries. Additionally, identification and characterization of thermal-hydraulic phenomena were performed for VVERs, ALWRs (including SMRs) and, also SCWRs with emphasize to the design specifics of these nuclear plants. A common list of 67 thermal-hydraulic phenomena including basic phenomena is provided for Separate Effects Tests (SETs), and Integral Test facilities (ITFs) of PWRs, BWRs, and VVERs have about 50 thermal-hydraulic phenomena. Additionally, Advanced Water-Cooled Reactors having 15 identified phenomena, as well as SCWRs (specifically HPLWR) related 6 more phenomena identified. For all these internationally agreed thermal-hydraulic phenomena either some detailed descriptions for selected cases are given or needed references are provided in the paper. These identified phenomena also help to define research needs in the related field for the major number of water-cooled reactors. The knowledge of the thermal-hydraulic phenomena is the backbone and essential part for the development of nuclear thermal-hydraulics subject area. Thus, the subject will be presented in two parts: Part I of the paper will be devoted to thermal-hydraulic phenomena related to SETs, PWRs, BWRs, and VVER-400 plus VVER-1000; Part II will be dealing with additional thermal-hydraulic phenomena for ALWRs including VVER-1200 and SMRs, and SCWRs which are covered under Gen-III + and GEN-IV designs.
机译：验证最佳估计的热工液压系统代码是证明其适用于计算核电站事故场景（包括事件过程）的适用性的必要步骤。它应证明对设计和安全分析目的适当地计算和分析了对核电站暂态和事故情景很重要的那些物理热工现象。在国际组织的框架内，e。 g。经济合作与发展组织核能安全设施委员会（OECD / NEA-CSNI）和国际原子能机构（IAEA），并在不同国家的机构的大力支持下，已经开展工作来建立压水堆和压水堆的单独效果测试（SET）设施和整体测试设施的验证矩阵。在此过程中，活动的主要内容之一是识别和表征热工现象，并测试类型。该过程基于所涉科学家的专业知识，并得到了不同国家的参与组织和机构的认可。此外，对VVER，ALWR（包括SMR）以及SCWR进行了热工现象的识别和表征，重点是这些核电站的设计细节。为单独的效果测试（SET）提供了包括基本现象在内的67种热工现象的通用列表，而PWR，BWR和VVER的集成测试设施（ITF）具有约50种热工现象。此外，先进的水冷堆具有15种已识别现象，以及与SCWR（特别是HPLWR）相关的6种以上已识别现象。对于所有这些国际上公认的热工现象，论文中都给出了一些具体案例的详细说明，或者提供了所需的参考资料。这些确定的现象也有助于确定相关领域对大量水冷堆的研究需求。对热工现象的认识是发展核热工学科领域的基础和必不可少的部分。因此，该主题将分为两个部分：论文的第一部分将致力于与SET，PWR，BWR和VVER-400加VVER-1000有关的热工现象。第二部分将讨论ALWR的其他热工现象，包括VVER-1200和SMR，以及在Gen-III +和GEN-IV设计中涉及的SCWR。

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  • 来源
    《Nuclear Engineering and Design》 |2019年第12期|110212.1-110212.22|共22页
  • 作者

    Aksan N.;

  • 作者单位

    Sci Consultant Haldenstr 35 CH-5415 Nussbaumen Switzerland;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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