Verification and Validation of the EUCLID/V2 Integrated Code’s HEFEST-FR Module

IF 0.9 Q4 ENERGY & FUELS
S. V. Tsaun, A. A. Butov, I. A. Klimonov, E. V. Moiseenko, N. A. Mosunova, V. F. Strizhov, E. V. Usov, V. I. Chukhno
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Abstract

For substantiating liquid metal cooled reactor plants, the EUCLID/V2 integrated code is being developed, and its verification and validation are carried out for certifying it at the Scientific and Technical Center for Nuclear and Radiation Safety (NTC NRB). One of the integrated code’s main parts is the severe accident block, which includes the SAFR module for calculating the destruction of fuel pins, fuel assemblies (FAs) and the entire core, as well as the HEFEST-FR module for calculating the melt retention and cooling down in the sodium-cooled reactor core catcher. The HEFEST-FR module implements the possibility to perform 2D simulation of the structural elements and fuel melt behavior in liquid metal cooled reactors. In accordance with the NTC NRB requirements, for the HEFEST-FR module to be used as part of the EUCLID/V2 code for analyzing the safety of fast reactors, it must be validated with the use of available experimental data; the validation shall be accompanied with an uncertainty and sensitivity analysis and assessment of the calculation result error. The article presents the results obtained from verification of the EUCLID/V2 integrated code HEFEST-FR module through solving the analytical problem of settling a stationary temperature of a homogeneous bounded cylinder uniformly heated from below with boundary conditions of the third kind and through solving the Stefan single-phase problem, as well as the results of validating the HEFEST-FR module based on the SCARABEE BF1 experiment. It is shown that the average absolute value by which the numerical calculation deviates from the analytical solution of the problem of settling a stationary temperature of a homogeneous bounded cylinder uniformly heated from below with boundary conditions of the third kind makes approximately 1.1 K. The maximum relative deviation of the results of calculations carried out using the computer program from the results of analytical solution of the Stefan problem (determination of the melt front) makes 0.46%. An assessment of the errors of modeling using the melt retention module as part of the EUCLID/V2 code (HEFEST-FR) based on the BF1 test of the SCARABEE experiment has shown that the temperature calculation error lies in the interval [‒82.3; 182.5] K, and the error of calculating the radial heat flux lies in the interval [‒55.2; 31.2] kW/m2.

Abstract Image

EUCLID/V2集成代码HEFEST-FR模块的验证和验证
为了验证液态金属冷却反应堆工厂,EUCLID/V2集成代码正在开发中,并在核与辐射安全科学技术中心(NTC NRB)进行验证和验证。集成代码的主要部分之一是严重事故模块,其中包括用于计算燃料销、燃料组件(FAs)和整个堆芯破坏的SAFR模块,以及用于计算钠冷却堆芯捕集器中的熔体保留和冷却的HEFEST-FR模块。HEFEST-FR模块实现了在液态金属冷却反应堆中对结构元件和燃料熔化行为进行二维模拟的可能性。根据NTC NRB的要求,HEFEST-FR模块作为EUCLID/V2代码的一部分用于分析快堆的安全性,必须使用可用的实验数据进行验证;验证应附有不确定度和灵敏度分析,并对计算结果误差进行评估。本文介绍了EUCLID/V2集成代码HEFEST-FR模块通过求解第三类边界条件下从下均匀加热的均匀有界圆柱体的定温解析问题和Stefan单相问题的验证结果,以及基于SCARABEE BF1实验对HEFEST-FR模块的验证结果。结果表明,在第三类边界条件下由下均匀加热的均匀有界圆柱体的定温问题的解析解与数值计算偏差的平均绝对值约为1.1 K。用计算机程序计算的结果与斯特凡问题(熔体前沿的确定)解析解的结果的最大相对偏差为0.46%。基于SCARABEE实验的BF1测试,对EUCLID/V2代码(HEFEST-FR)中熔体保持模块的建模误差进行了评估,结果表明:温度计算误差位于[-82.3;182.5] K,径向热流密度计算误差在[-55.2;31.2千瓦/ m2。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.30
自引率
20.00%
发文量
94
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