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Improvement of Core Modeling in ICARE/CATHARE: Application to the Calculation of a Six-Inch-Break LOCA Leading to a Severely Degraded Situation

机译:改进ICARE / CATHARE中的​​核心模型:将其应用到导致严重退化的六英寸断裂LOCA的计算中

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摘要

In order to analyze the course of a hypothetical severe accident, the French "Institut de Radioprotection et de Surete Nucleaire" in the last decade has developed computer codes that have been extensively used for supporting the Level 2 Probabilistic Safety Assessment (PSA2) and, in general, for the safety analysis of French pressurized water reactors (PWRs).rnIn particular, the computer code ICARE/CATHARE VI is a tool that has been widely validated and intensively used within the framework of the PSA2 of the 900-MW(electric) French PWR. This code has been tested on many accident scenarios, and the results obtained have been considered to be satisfactory and reliable up to the end of the early degradation phase. But, severe accidents in PWRs are characterized by a continuous evolution of the core geometry due to chemical reactions, melting, and mechanical failure of the rods and other structures. These local variations of the porosity and other parameters lead to multidimensional flows and heat transfers. So, the lack of a multidimensional two-phase thermal-hydraulic model appeared to be prejudicial to achievernbest-estimate reactor studies with ICARE/CATHARE VI in the case of large core blockages and/or in the case of large cavity appearance. In accordance, a full multidimensional modeling (covering both the fluid flow and the corium behavior) was developed and introduced in a new ICARE/CATHARE version referenced as V2, which includes two options for the thermal-hydraulic modeling: either one-dimensional (ID) or two-dimensional (2D).rnThe first part of this paper demonstrates that without activating the new V2 models, ICARE/CATHARE V2(1D) is able to reproduce the results obtained with ICARE/ CATHARE VI on the basis of a 6-in.-break loss-of-coolant accident. Then, in order to illustrate some of the new V2 modeling improvements, the last part is focused on the results obtained with ICARE/CATHARE V2(2D), and a preliminary comparison is made with ICARE/ CATHARE V2(1D).rnThis 1D-2D comparison points out in particular the important role that could be played in the course of a severe accident by the multidimensional flow pattern.
机译:为了分析假设的严重事故的过程,法国“放射防护和核医学研究所”在过去十年中开发了计算机代码,这些代码已广泛用于支持2级概率安全评估(PSA2),并且一般而言,用于法国压水堆(PWR)的安全分析.rn特别地,计算机代码ICARE / CATHARE VI是一种工具,已在900兆瓦(电)的PSA2框架内得到广泛验证和广泛使用法国压水堆。该代码已经在许多事故场景下进行了测试,并且直到早期降解阶段结束为止,所获得的结果都被认为是令人满意和可靠的。但是,压水堆严重事故的特征是,由于棒和其他结构的化学反应,熔化和机械故障,铁心的几何形状不断演变。孔隙率和其他参数的这些局部变化导致多维流动和热传递。因此,在大型堆芯堵塞情况下和/或在大型型腔情况下,缺乏多维两相热工液压模型似乎不利于用ICARE / CATHARE VI获得最佳估计的反应堆研究。因此,开发了完整的多维模型(涵盖了流体流动和皮质行为),并将其引入了称为V2的新ICARE / CATHARE版本中,该版本包括热工液压建模的两个选项:一维(ID )或二维(2D)。rn本文的第一部分说明了ICARE / CATHARE V2(1D)无需激活新的V2模型,就可以在6-基础上重现使用ICARE / CATHARE VI获得的结果。破裂中冷却液损失事故。然后,为了说明一些新的V2建模改进,最后一部分着重于使用ICARE / CATHARE V2(2D)获得的结果,并与ICARE / CATHARE V2(1D)进行了初步比较。 2D比较特别指出了多维流型在严重事故过程中可能发挥的重要作用。

著录项

  • 来源
    《Nuclear Technology》 |2009年第1期|235-246|共12页
  • 作者单位

    Institut de Radioprotection et de Surete Nucleaire, CE Cadarache, Bat. 700, 13115 Saint Paul Lez Durance, France;

    Institut de Radioprotection et de Surete Nucleaire, CE Cadarache, Bat. 700, 13115 Saint Paul Lez Durance, France;

    Institut de Radioprotection et de Surete Nucleaire, CE Cadarache, Bat. 700, 13115 Saint Paul Lez Durance, France;

    Institut de Radioprotection et de Surete Nucleaire, CE Cadarache, Bat. 700, 13115 Saint Paul Lez Durance, France;

    Institut de Radioprotection et de Surete Nucleaire, CE Cadarache, Bat. 700, 13115 Saint Paul Lez Durance, France;

  • 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
  • 中图分类
  • 关键词

    severe accidents; multidimensional thermal hydraulics; ICARE/CATHARE;

    机译:严重事故;多维热力液压;ICARE /浴室;

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