首页> 外文会议>International conference on nuclear engineering >MODELLING THE NEUTRONICS OF A MOLTEN SALT FAST REACTOR USING DYN3D-MG FOR THE INVESTIGATION OF THE APPLICATION OF FROZEN WALL TECHNOLOGY
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MODELLING THE NEUTRONICS OF A MOLTEN SALT FAST REACTOR USING DYN3D-MG FOR THE INVESTIGATION OF THE APPLICATION OF FROZEN WALL TECHNOLOGY

机译:使用DYN3D-MG建模盐溶快中子的神经元,研究冻结墙技术的应用

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Molten salt reactors are a very promising option for the development of highly innovative solutions for the nuclear energy production of the future. New results of the application of the nodal diffusion code, DYN3D-MG, to model the steady state operation of molten salt fast reactors based on circulating fluoride salt, are presented here. The cross-section set was prepared using the Monte Carlo particle transport code, SERPENT. Full core comparisons between SERPENT and DYN3D-MG demonstrate that the molten salt fast reactor steady state operation can be modelled by DYN3D-MG within the required accuracy. The work is an important initial step for the development of a coupled CFDeutron physics code system. This code system will finally be applied for the investigation of an innovative material protection scheme to avoid the contact of the liquid salt with the structural material.
机译:熔盐反应堆是为未来的核能生产开发高度创新的解决方案的一个非常有前途的选择。本文介绍了应用节点扩散码DYN3D-MG来模拟基于循环氟化物盐的熔盐快堆稳态运行的新结果。使用蒙特卡洛粒子传输代码SERPENT来准备横截面集。 SERPENT和DYN3D-MG之间的全堆芯比较表明,DYN3D-MG可以在所需的精度内对熔盐快堆稳态运行进行建模。这项工作是开发耦合CFD /中子物理代码系统的重要的第一步。该代码系统最终将用于研究创新的材料保护方案,以避免液态盐与结构材料接触。

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