为控制美国补充临界水反应堆(SCWR)的反应性寻找最佳设计和可燃烧吸收器

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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引用次数: 0

摘要

超临界水反应堆(SCWR)被公认为第四代核反应堆设计的基石,目前正在进行大量的研究工作,以推动其发展。评估和管理反应堆的反应性是反应堆运行中的一个重要问题。这项研究旨在确定有效的可燃吸收剂(BA)材料,并确定燃料组件内的最佳空间分布,以有效调节反应性水平。钆、铒和镥被建议以整体可燃吸收剂(IBA)棒((UO + GdO)、(UO + ErO) 和 (UO + LuO))的形式作为可燃吸收剂。对两种 SCWR 组件模型进行了研究,每种模型都具有不同数量和分布的 BA。在所建议的模型中,对所建议的 BA 的各种浓度进行了研究,以验证最佳情况。还进行了燃烧分析,以评估所建议的情况。研究了控制棒中的不同 BA 合金,包括 BC+DyO 和 BC+SmO,并与标准合金 BC 进行了比较。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Searching for optimum design and burnable absorber for controlling the reactivity of u.s. Supper critical water reactor (SCWR)

Numerous research endeavours are currently underway to advance supercritical water reactors (SCWR), acknowledged as a cornerstone among Generation IV nuclear reactor designs. Evaluation and managing the reactivity of the reactor is a vital issue in the reactor operation. This research seeks to identify efficacious burnable absorber (BA) materials and determine an optimal spatial distribution within the fuel assembly to regulate reactivity levels effectively. Gadolinium, erbium and Lutetium have been suggested as BA in the form of integral burnable absorber (IBA) rods ((UO2 + Gd2O3), (UO2 + Er2O3) and (UO2 + Lu2O3)). Two SCWR assembly models, each featuring varied quantities and distributions of BA, have been examined. Various concentrations of the suggested BAs have been examined in the suggested models to verify the optimum cases. Burnup analyses have been conducted to evaluate the proposed cases. Different alloys of BAs including B4C+Dy2O3 and B4C+Sm2O3 have been investigated in the control rod and compared with the standard alloy B4C.

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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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