D-LOFC后高温气冷堆进气口热工力学研究现状综述

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Matthew Scheel , Piyush Sabharwall , Richard Schultz , Daniele Ludovisi , Gianluca Blois
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引用次数: 0

摘要

考虑到高温气冷堆(htgr)固有的被动安全特性和高热效率,随着人们对碳中和的期望接近立即实现,广泛实施高温气冷堆(htgr)是一种可行的解决方案。本研究概述了htgr中减压强迫冷却损失(D-LOFC)导致空气进入的热工水力学研究现状。准确地描述和预测空气进入的物理现象是最重要的,因为燃料和芯石墨支撑结构的完整性受到氧气存在的威胁。从广义上讲,空气进入场景可以分为三个主要阶段:(1)降压,(2)密度驱动流,(3)自然对流。与潜在的基本理论相结合,本综述整理和综合了关于D-LOFC后空气进入情景的现有当代研究。正如这篇综述所证明的那样,我们目前的理解和预测能力得益于广泛的研究,主要集中在空气吸入核心的速度上。通过考虑额外的变量:进入空气的氧含量,需要进行额外的研究,以全面捕捉D-LOFC后空气进入情景的现象学。后一个变量需要对完全集成系统的复杂相互作用进行研究。此外,虽然数值工具正在通过核能高级建模和仿真计划在国内发展,但仍然缺乏充分验证的代码。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC
With the expectation of near-immediate carbon neutrality, widespread implementation of proven High-Temperature Gas-cooled Reactors (HTGRs) embodies a viable solution pathway given their inherent, passive safety features and high thermal efficiency. This study provides an overview of the current state of research involving the thermal hydraulics associated with air ingress from a depressurized loss of forced cooling (D-LOFC) in HTGRs. Accurately characterizing and predicting the physical phenomena underlying air ingress is of paramount concern, as the integrity of the fuel and core graphite support structures are threatened by the presence of oxygen. Broadly speaking, the air ingress scenario can be delineated into three main stages: (1) Depressurization, (2) Density-Driven Flow, and (3) Natural Convection. In tandem with the underlying fundamental theory, this review collates and synthesizes the existing body of contemporary research concerning the air ingress scenario following a D-LOFC. As evinced by this review, our current understanding and predictive abilities have benefited from extensive research, predominantly concentrated on the rate of air ingestion into the core. Additional research is necessary to holistically capture the phenomenology of an air ingress scenario following a D-LOFC by considering an additional variable: the oxygen content of the ingressing air. The latter variable requires investigation into the complex interactions of the fully integrated system. Additionally, while numerical tools are evolving domestically through the Nuclear Energy Advanced Modeling and Simulation program, a sufficiently validated code remains absent.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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