Physics analysis and design of heavy water reflected thermal test reactor

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-10-24 DOI:10.1016/j.anucene.2024.110966
Hikaru Hiruta, Mark D. DeHart, Carlo Parisi
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Abstract

This work investigates the option of modifying the Advanced Test Reactor by replacing the current beryllium reflector with heavy water. Such a change may provide some potential benefits for not only increasing the thermal irradiation capabilities but also resolving other problems such as reflector integrity issues due to fast fluence damage, which is always a limiting factor in the lifetime of the current beryllium reflector. This paper presents the analysis and estimation of the ATR core physics parameters by replacing the current beryllium reflector with heavy water (D2O). The paper first describes the details of two selected conceptual designs, which are partially reflected with either beryllium or graphite, and how they are derived from the baseline beryllium reflector concept. Then, reactor physics performance parameters for the two new concepts are assessed by comparing with those of the baseline concept. The performance parameters considered in this paper include in-pile tube neutron and gamma fluxes and heating rates, maximum loop voiding reactivity, core power behavior with different power splits, predicted cycle length with a given fuel loading, and thermal hydraulic analysis with a higher lobe power split. It is important to note that this study focuses on the reactor physics aspects and does not delve into the engineering challenges associated with such a design modification.
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重水反射热试验反应堆的物理分析和设计
这项工作研究了用重水取代现有铍反射器来改造先进试验反应堆的方案。这种改变不仅可以提高热辐照能力,还可以解决其他问题,如快速通量损伤导致的反射器完整性问题,而快速通量损伤一直是当前铍反射器寿命的限制因素。本文介绍了用重水(D2O)取代当前铍反射器后对 ATR 核心物理参数的分析和估算。本文首先介绍了两种选定概念设计的细节,它们部分采用铍或石墨反射,以及如何从基线铍反射器概念中衍生出来。然后,将这两种新概念的反应堆物理性能参数与基线概念的性能参数进行比较评估。本文考虑的性能参数包括堆内管中子通量和伽马通量及加热率、最大环路空化反应性、不同功率分流下的堆芯功率行为、给定燃料装载下的预测循环长度,以及较高叶功率分流下的热水力分析。值得注意的是,本研究侧重于反应堆物理方面,并未深入探讨与此类设计修改相关的工程挑战。
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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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