Simulation of Melt Behavior in the Sodium-Cooled Reactor Core Catcher Using the EUCLID/V2 Integrated Computer Code HEFEST-FR Module

IF 0.9 Q4 ENERGY & FUELS

Thermal Engineering Pub Date : 2023-11-08 DOI:10.1134/S0040601523110034

A. A. Butov, D. D. Kamenskaya, I. A. Klimonov, N. A. Mosunova, E. V. Usov, S. V. Tsaun, V. I. Chukhno

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Abstract—

For numerically simulating the melt behavior in the core catcher of a sodium-cooled reactor, the HEFEST-FR module—a software tool based on the SAFR computer code elaborated at the Nuclear Safety Institute, Russian Academy of Sciences, for simulating the meltdown and destruction of liquid metal-cooled fast reactor core components—has been developed and incorporated into the EUCLID/V2 integrated computer code. This module is intended for numerically simulating the melt retention and cooling-down processes in the reactor vessel with taking into account the heat transfer from the vessel’s internal structures to the coolant. For this purpose, a 2D-problem (implying that there is no dependence of temperature on the azimuthal angle) of unsteady heat conduction for materials located in the reactor’s core catcher tray is solved in a cylindrical coordinate system. The heat-conduction equation coefficients depend on time, coordinates, and temperature, the latter being the solution of equation. Boundary conditions of the first, second, and third kind are used, and heat loss by radiation at the boundary is specified. The total or volumetric decay heat power is given inside of the melt. For numerically solving the 2D heat-conductivity problem, an enthalpy approach based method is applied. The formulations used in the method make it possible to overcome, in a natural manner, the problem relating to discontinuity of material specific melting point enthalpy in solving the heat-conduction problem with taking phase transitions into account. The solution yields the temperature field in melting/freezing of materials (steels of various grades and fuel) in the fast reactor’s core catcher tray. The results of verifying the HEFEST-FR module against the solution of an analytical problem have been demonstrated. Using the module, methodical computations of the fuel and fuel pin cladding melt behavior in the sodium-cooled reactor’s core catcher have been carried out.

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使用EUCLID/V2集成计算机代码HEFEST-FR模块模拟钠冷堆堆芯捕集器中的熔体行为

摘要——为了对钠冷却反应堆堆芯捕集器中的熔体行为进行数值模拟，HEFEST-FR模块是一种基于俄罗斯科学院核安全研究所开发的SAFR计算机代码的软件工具，用于模拟液态金属冷却快堆堆芯部件的熔毁和破坏——已经开发并纳入EUCLID/V2集成计算机代码中。该模块旨在数值模拟反应堆容器中的熔体保持和冷却过程，同时考虑从容器内部结构到冷却剂的热传递。为此，在圆柱形坐标系中解决了反应堆堆芯捕集器托盘中材料的非稳态热传导的2D问题（意味着温度与方位角无关）。热传导方程的系数取决于时间、坐标和温度，后者是方程的解。使用第一种、第二种和第三种边界条件，并规定了边界处的辐射热损失。总衰变热功率或体积衰变热功率在熔体内部给出。为了数值求解二维导热系数问题，采用了基于焓法的方法。该方法中使用的配方可以以自然的方式克服在考虑相变的情况下解决热传导问题时与材料比熔点焓的不连续性有关的问题。该溶液产生了快堆堆芯捕集器托盘中材料（各种等级的钢和燃料）熔化/冻结时的温度场。已经证明了根据分析问题的解决方案验证HEFEST-FR模块的结果。使用该模块，对钠冷堆堆芯捕集器中的燃料和燃料针包壳熔体行为进行了系统的计算。

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来源期刊

Thermal Engineering Multiple-

CiteScore

1.30

自引率

20.00%

发文量