Analysis of zirconium hydride moderator effect on the micro lead-based reactor

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-23 DOI:10.1016/j.anucene.2024.110883
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Abstract

As a crucial parameter for the design of micro reactors, the neutron spectrum directly impacts the keff, the critical size, burnup characteristics, reactivity temperature coefficients and so on. When considering the optimization of the reactor size, designs utilizing thermal neutron spectrum and fast neutron spectrum each present their unique advantages and challenges. To investigate the impact of energy spectrum on the reactor performance, a micro lead-based reactor with annular channel fuel elements is proposed and the study of the influence of varying the volume ratio of moderator and fuel (the M/F ratio) on the keff, the critical size, burnup characteristic and reactivity temperature coefficients by using the Reactor Monte Carlo code (RMC code) is conducted. The results show that for the micro lead-based reactor proposed, when the reactor energy output demand is greater than 350 MWt·years, the design with fast neutron spectrum (without moderator) exhibits the minimum size. While the reactor energy output demand is less than 350 MWt·years, the design with a thermal neutron spectrum (with moderator) achieves the minimum size. Moreover, to ensure the negative reactivity temperature effect, the M/F ratio should be maintained below 3.4. The insights presented in this paper will serve as valuable references for the design of the micro reactor.

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锆氢化物慢化剂对微型铅基反应堆的影响分析
作为微型反应堆设计的一个关键参数,中子谱直接影响到 Keff、临界尺寸、燃烧特性、反应温度系数等。在考虑优化反应堆尺寸时,利用热中子能谱和快中子能谱的设计各有其独特的优势和挑战。为了研究能谱对反应堆性能的影响,我们提出了一种采用环形通道燃料元件的微型铅基反应堆,并利用反应堆蒙特卡洛代码(RMC 代码)研究了改变慢化剂和燃料的体积比(M/F 比)对 Keff、临界尺寸、燃烧特性和反应温度系数的影响。结果表明,对于所提出的微型铅基反应堆,当反应堆能量输出需求大于 350 兆瓦特年时,快中子谱设计(无慢化剂)显示出最小尺寸。当反应堆能量输出需求小于 350 兆瓦年时,热中子能谱设计(带慢化剂)可实现最小规模。此外,为确保负反应温度效应,M/F 比应保持在 3.4 以下。本文提出的见解将为微型反应堆的设计提供有价值的参考。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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