Neutron codes for calculating advanced reactor plants with a liquid metal coolant

IF 0.3 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2025-03-03 DOI:10.1007/s10512-025-01178-z
A. A. Belov, V. P. Bereznev, D. A. Koltashev, V. S. Potapov, O. I. Chertovskikh
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Abstract

Numerical simulation based on contemporary computational codes represents a current trend for the safety justification of existing and planned nuclear power facilities including reactor plants with liquid metal coolants. The present study considers neutron codes developed by IBRAE RAN under the Proryv project direction. The paper discusses CORNER and ODETTA codes based on the discrete ordinate method, the BPSD code for isotope kinetics, activity and decay heat calculation, EVKLID/V1 and EVKLID/V2 integral codes, as well as the COMPLEX software system for substantiating nuclear and radiation safety.

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用于计算采用液态金属冷却剂的先进反应堆设备的中子代码
基于当代计算规范的数值模拟代表了现有和计划中的核设施(包括使用液态金属冷却剂的反应堆)安全论证的当前趋势。本研究考虑了在Proryv项目方向下由IBRAE RAN开发的中子码。本文讨论了基于离散坐标法的CORNER和ODETTA代码,同位素动力学、活度和衰变热计算的BPSD代码,EVKLID/V1和EVKLID/V2积分代码,以及核与辐射安全实证的COMPLEX软件系统。
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
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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