CALCULATION OF THE STRUCTURAL MATERIALS ACTIVATION BY A FUSION NEUTRON FLUX WITH BPSD CODE

PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS Pub Date : 2021-12-26 DOI:10.55176/2414-1038-2021-4-47-62

A. Belov, M. Kryachko, O. Chertovskikh, A. Ivanov

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引用次数: 1

Abstract

The calculation of activation inventories is one of the key aspects in nuclear plants simulation. Burnup calculations provide information not only about fuel actinides transmutation but also about impact of fuel/constructor materials/coolant impurities on the material. The inventory evolution also determines radiological response of a material by nuclides production/decay rates quantification. Results of the isotopic kinetics code BPSD for activity and afterheat calculation validation by means of direct comparison afterheat obtained by code BPSD with experimental data obtained due to steel SS-304 and steel SS-316 samples irradiation by fusion neutron spectra at the FNS facility and with results of FISPACT-II calculation are presented in this paper. BPSD code is intended for carrying of transmutation calculations of materials in fast neutron fluxes. Nuclides transformation chains are based on ROSFOND and ABBN-RF data. BPSD and FISPACT-II calculations results conform to each other. Differences in results could be explained by differences between transformation chains and by using different evaluation neutron data bases.

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用BPSD程序计算核聚变中子通量活化结构材料

激活清单的计算是核电厂仿真的关键问题之一。燃耗计算不仅提供有关燃料锕系元素嬗变的信息，而且还提供有关燃料/构造材料/冷却剂杂质对材料的影响的信息。库存演变还通过核素产生/衰变率量化来确定材料的放射性响应。本文介绍了同位素动力学代码BPSD对活度和余热计算的验证结果，通过直接比较代码BPSD获得的余热与FNS设施中SS-304钢和SS-316钢样品的聚变中子谱辐照实验数据以及FISPACT-II计算结果。BPSD代码用于承载快中子通量中物质的嬗变计算。核素转化链基于ROSFOND和ABBN-RF数据。BPSD和FISPACT-II的计算结果基本一致。结果的差异可以由转换链的不同和使用不同的评价中子数据库来解释。

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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PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS

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