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使用小于 10%浓缩二氧化铀燃料的先进高温钠冷热堆

IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY
Nuclear Science and Engineering Pub Date : 2024-08-30 DOI:10.1080/00295639.2024.2381387
Gilles Youinou
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引用次数: 0

摘要

本文介绍了一个 1200 兆瓦（热）先进钠冷热堆概念，该概念采用 3.5% 至 9.95% 的浓缩二氧化铀燃料针束在线加料；使用石墨或铍氧化物；使用铌或钽燃料；使用铌或钽......
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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Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO2 Fuel
This paper presents a 1200-MW(thermal) advanced sodium-cooled thermal reactor concept that uses online refueling of 3.5% to 9.95% enriched UO2 fuel pin bundles; uses either graphite or beryllium ox...
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来源期刊
Nuclear Science and Engineering
Nuclear Science and Engineering 工程技术-核科学技术
CiteScore
2.10
自引率
25.00%
发文量
0
审稿时长
3 months
期刊介绍： Nuclear Science and Engineering, the research journal of the American Nuclear Society, publishes articles on research and development related to peaceful utilization of nuclear energy, radiation, and alternative energy sources.
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