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Neutronic analysis of high burnup thorium-HALEU fuels in PHWR
Nuclear Engineering and Design ( IF 1.7 ) Pub Date : 2024-03-26 , DOI: 10.1016/j.nucengdes.2024.113113
N. Read , V. Raffuzzi

Recent developments have been made in a novel fuel for pressurised heavy water reactors: high burnup oxide fuels composed of a mixture of thorium and high assay low enriched uranium. Several claims are made regarding the performance of such fuels in terms of economics, waste and non-proliferation, among others. This article analyses this class of fuel using an infinite lattice study in SERPENT. First, a set of fuel compositions in the thorium/uranium enrichment design space that satisfy the high burnup target is produced. Then, a representative thorium-based fuel is compared to a uranium-only fuel with the same discharge burnup, as well as current standard fuel, in the context of the various performance claims.

中文翻译:

PHWR 中高燃耗钍-HALEU 燃料的中子分析

最近在用于加压重水反应堆的新型燃料方面取得了进展:由钍和高含量低浓缩铀混合物组成的高燃耗氧化物燃料。人们对此类燃料在经济性、废物利用和防扩散等方面的性能提出了一些主张。本文使用 SERPENT 中的无限晶格研究来分析此类燃料。首先,在钍/铀浓缩设计空间中生产出满足高燃耗目标的一组燃料组合物。然后,在各种性能声明的背景下,将代表性的钍基燃料与具有相同放电燃耗的纯铀燃料以及当前标准燃料进行比较。
更新日期:2024-03-26
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