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首页> 外文期刊>Annals of nuclear energy >More conservative governing equations in RELAP5: Derivation of equations
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More conservative governing equations in RELAP5: Derivation of equations

机译:RELAP5中更保守的控制方程:方程的推导

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摘要

The design and analysis of the thermal/hydraulic systems in nuclear power plants necessitate system codes that can be used in the analysis of steady state and transient conditions. RELAP5 is one of the most commonly used system codes in nuclear organizations. RELAP5 is based on a two-fluid, non-equilibrium, non-homogeneous, hydrodynamic model for the transient simulation of the two-phase system behavior. This model includes six governing equations to describe the mass, energy, and momentum of the two fluids. The "non-conservative" numerical approximation form (which is the current version of RELAP5 code) is obtained through the manipulation of selected derivative terms in the equations including the linearization of the product terms in the time derivatives of the equations. In the non-conservative technique, the truncation errors introduced in the linearization process can produce mass and energy errors for some classes of transients during time advancements, either resulting in (a) automatic reduction of time steps used in the advancement of the equations and increased run times or (b) the growth of unacceptably large errors in the transient results. To eliminate these difficulties, an optional numerical approach has been introduced in RELAP/SCDAPSIM/MOD4.0. This approach uses a more consistent set of "conservative" numerical approximations to solve non-linearized mass and energy governing equations. The RELAP/SCDAPSIM/MOD4.0 code, being developed as part of the international Severe Core Damage Analysis Package (SCDAP) Development and Training Program (SDTP), is the first version of RELAP5 rewritten to FORTRAN 90/95/2000 standards. This paper provides an overview of the original RELAP5 numerical approximations and describes the new theoretical approach. The second article introduces the strategic solution of the more conservative approach and presents some examples of transient problems that have been addressed utilizing this new approach. (C) 2015 Elsevier Ltd. All rights reserved.
机译:核电厂热力/液压系统的设计和分析需要使用可用于分析稳态和暂态条件的系统代码。 RELAP5是核组织中最常用的系统代码之一。 RELAP5基于两流体,非平衡,非均匀,水动力模型,用于两相系统行为的瞬态仿真。该模型包括六个控制方程式,用于描述两种流体的质量,能量和动量。 “非保守”数值逼近形式(这是RELAP5代码的当前版本)是通过操纵方程中选定的导数项(包括对方程的时间导数中的乘积项进行线性化)获得的。在非保守技术中,线性化过程中引入的截断误差会在时间提前过程中对某些类别的瞬变产生质量和能量误差,从而导致(a)自动减少用于方程式进展的时间步长并增加运行时间或(b)瞬态结果中出现不可接受的大误差。为了消除这些困难,RELAP / SCDAPSIM / MOD4.0中引入了一种可选的数值方法。此方法使用一组更一致的“保守”数值逼近来求解非线性质量和能量控制方程。 RELAP / SCDAPSIM / MOD4.0代码是作为国际严重核心损坏分析软件包(SCDAP)开发和培训计划(SDTP)的一部分开发的,是重写为FORTRAN 90/95/2000标准的RELAP5的第一个版本。本文提供了原始RELAP5数值近似的概述,并描述了新的理论方法。第二篇文章介绍了较为保守的方法的战略解决方案,并提供了一些使用此新方法已解决的暂时性问题的示例。 (C)2015 Elsevier Ltd.保留所有权利。

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