Neutronics evaluation for coating layers of the blanket system in a hybrid fusion-fission reactor

IF 3.2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-09-09 DOI:10.1016/j.pnucene.2025.106010

Natália G.P. L. Oliveira, Claubia Pereira

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引用次数: 0

Abstract

A hybrid fusion-fission reactor (FFH) can be understood as a significant source of fusion neutrons combined with a layer of fissile fuel, which can be used both for the breeding of fissile material and for the transmutation of high-level radioactive waste (HLW), such as the long half-life actinide elements. To evaluate an FFH reactor for the transmutation of reprocessed fuel, two models of an FFH are analyzed: a simpler model for the plasma chamber without the representation of the divertor component (Model 1) and a model with the divertor component represented in a simplified form (Model 2). This work aims to analyze changes in the spectrum of fusion neutrons that reach the transmutation layers (TL) position in the two simulated FFH reactor models, investigating the albedo coefficients calculated through the input and output currents in the beryllium coating layers, heat sink, and tritium production. Differences in the interactions of neutrons with these three layers are observed between the models, initially caused by the scattering of fusion neutrons with the W nuclei of the diverter's plasma facing components (PFC), which can ultimately impact the transmutation rate and energy multiplication between models.

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混合聚变裂变反应堆包层系统包层的中子学评价

混合聚变-裂变反应堆（FFH）可以理解为一个重要的聚变中子来源，结合一层可裂变燃料，既可用于裂变材料的增殖，也可用于高放射性废物（HLW）的嬗变，如长半衰期的锕系元素。为了评估用于后处理燃料嬗变的FFH反应堆，我们分析了两种FFH模型：一种是不含转化器组件的等离子体室的简单模型（模型1），另一种是用简化形式表示转化器组件的模型（模型2）。本工作旨在分析两种模拟FFH反应堆模型中到达嬗变层（TL）位置的聚变中子谱的变化，研究通过铍涂层、散热器和氚生成的输入和输出电流计算的反照率系数。中子与这三层的相互作用在不同的模型之间存在差异，最初是由于核聚变中子与分流器等离子体面组件（PFC）的W核散射造成的，这最终会影响模型之间的嬗变速率和能量倍增。

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

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.