利用 240Pu 自发裂变源开发测量延迟中子有效部分的方法

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Atomic Energy Pub Date : 2024-10-11 DOI:10.1007/s10512-024-01137-0

V. A. Grabezhnoy, V. A. Dulin, G. M. Mikhailov

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引用次数: 0

摘要

文章介绍了对燃料由金属钚、贫化铀氮化物和二氧化物组成的 BFS 临界组件的延迟中子有效部分 βeff 的测定结果。通过将 252Cf 源引入堆芯来确定 βeff 的传统方法得到了燃料成分中自发裂变的 240Pu 源的补充。所描述的修改简化了分析，提高了结果的可靠性，并可用于不可能使用 252Cf 源的已知成分钚功率堆。

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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Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source

The article presents the results of determining the effective fraction of delayed neutrons β_eff for a BFS critical assembly whose fuel is composed of metallic plutonium and depleted uranium nitride and dioxide. The traditional method for determining β_eff by introducing the ²⁵²Cf source into the core is supplemented by the ²⁴⁰Pu source of spontaneous fissions in the fuel composition. The described modification simplifies the analysis, increases the reliability of results, and can be used in power reactors with plutonium of known composition in which it is impossible to use a ²⁵²Cf source.

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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.