首页> 外文会议>International conference on nuclear engineering;ICONE17 >NEXT GENERATION SAFETY ANALYSIS METHODS FOR SFRS (3) THERMAL HYDRAULICS MODELS OF COMPASS CODE AND EXPERIMENTAL ANALYSES
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NEXT GENERATION SAFETY ANALYSIS METHODS FOR SFRS (3) THERMAL HYDRAULICS MODELS OF COMPASS CODE AND EXPERIMENTAL ANALYSES

机译:SFRS的下一代安全分析方法(3)指南针热工水力模型和实验分析

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A computer code, named COMPASS, is being developed employing the Moving Particle Semi-implicit (MPS) method for various complex phenomena of core disruptive accidents (CDAs) in the sodium-cooled fast reactors (SFRs). The COMPASS is designed to analyze multi-physics problems involving thermal hydraulics, structure and phase change, in a unified framework of MPS method. In FYs2006 and 2007 (Japanese Fiscal Year, hereafter), the development of basic functions of COMPASS was completed and fundamental verification calculations were carried out. In FY2007, the integrated verification program using available experimental data for key phenomena in CDAs was also started.In this paper, we show the basic verification calculations for the phase change model of COMPASS and the results of experimental analyses, together with the outline of the formulation of MPS method and the conceptual design of the COMPASS code.
机译:正在使用移动粒子半隐式(MPS)方法开发一种名为COMPASS的计算机代码,用于处理钠冷快堆(SFR)中堆芯破坏性事故(CDA)的各种复杂现象。 COMPASS设计用于在MPS方法的统一框架中分析涉及热力学,结构和相变的多物理场问题。在2006财政年度和2007财政年度(以下称日本财政年度),COMPASS基本功能的开发完成,并进行了基本验证计算。在2007财政年度,也开始了使用CDA关键现象的可用实验数据的综合验证程序。 在本文中,我们将展示COMPASS相变模型的基本验证计算和实验分析结果,以及MPS方法的制定概述和COMPASS代码的概念设计。

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