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

IF 0.4 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

引用次数: 0

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

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来源期刊

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.