An approach to Molten Salt Reactor operation and control and its application to the ARAMIS actinide burner

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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Abstract

Molten salt reactors (MSRs) are Generation IV nuclear reactor concepts gaining significant research interest worldwide. The present work proposes a methodology for the definition and optimization of the MSR operating conditions and control strategy. The proposed methodology employs a novel 0D steady-state model, the multi-physics system-scale MOSAICS (MOlten SAlt Incompressible Calculation System) model and a Global Sensitivity Analysis (GSA) method based on Hilbert-Schmidt Independence Criterion indices. The methodology was then applied to the ARAMIS (Advanced Reactor for Actinides Management in Salt) fast-spectrum chloride-salt burner reactor. Two alternative control strategies are proposed in order to achieve target margins to the salt freezing and structure material limit temperatures during normal operation, plus a 20 % power variation per minute load-following objective. The performance of the control strategies was assessed through comparison with the natural behavior during a load-increasing transient, as well as during Unprotected Transient Over-Power (UTOP) and Station Blackout (SBO) accidents. Controlled load variation transients are observed to reduce overall temperature variation rates throughout the salt circuits, while the inclusion of a variable fuel flow from the reactor commands can further limit these fluctuations. However, the selected operating conditions exhibited insufficient margins to freezing or the materials limit temperature under unprotected accident conditions. GSA enabled the derivation of correlations to characterize the dynamic response of MSRs to the accidents. Based on the observed reactor response to the various transients, potential modifications to the ARAMIS design and control strategies are proposed.

熔盐反应堆运行和控制方法及其在阿 拉米斯锕系元素燃烧器中的应用
熔盐反应堆(MSR)是第四代核反应堆概念,在全球范围内引起了极大的研究兴趣。本研究提出了一种定义和优化 MSR 运行条件和控制策略的方法。该方法采用了一种新颖的 0D 稳态模型、多物理场系统尺度 MOSAICS(MOlten SAlt Incompressible Calculation System)模型和基于希尔伯特-施密特独立标准指数的全局敏感性分析(GSA)方法。然后将该方法应用于 ARAMIS(盐中锕系元素管理先进反应堆)快速光谱氯盐燃烧器反应堆。提出了两种替代控制策略,以实现正常运行期间盐冻结温度和结构材料极限温度的目标裕度,以及每分钟 20% 的功率变化负荷跟踪目标。通过与负载增加瞬态期间的自然行为以及无保护瞬态过功率(UTOP)和电站停电(SBO)事故期间的自然行为进行比较,对控制策略的性能进行了评估。据观察,受控的负载变化瞬态可降低整个盐回路的总体温度变化率,而反应堆指令中包含的可变燃料流可进一步限制这些波动。然而,在无保护事故条件下,所选运行条件显示出与冻结或材料极限温度之间的余量不足。GSA 能够推导出相关关系,以描述 MSR 对事故的动态响应。根据观察到的反应堆对各种瞬态的响应,提出了对 ARAMIS 设计和控制策略的潜在修改建议。
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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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