全面概述超临界流体自然循环回路的进展、应用和影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Santosh Kumar Rai , Pardeep Kumar , Mukesh Tiwari , Vinay Panwar , Dinesh Kumar , Vipin Kumar Sharma
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引用次数: 0

摘要

如今,许多研究都在不断探索如何理解超临界流体自然循环回路(SCFNCL)的各种特性,如在正常运行条件下使用 SCFNCL 作为被动系统从堆芯中带走热量、回路的稳态和瞬态行为、传热速率、传热系数以及优化回路的质量流量。在过去的二十年里,通过分析、计算和实验工作,已经开展了大量的研究工作,这些工作强调了在核电厂(NPPs)中将 SCFNCL 作为主动和被动系统的显著用途。然而,基于回路几何形状及其影响、不同类型的超临界流体 (SCF) 以及回路应用的研究成果非常有限。因此,本综述的重点是单通道和平行通道环路的稳定和瞬态行为、热液(TH)不稳定性、几何和运行参数对 SCFNCL 的影响以及 SCFNCL 的传热恶化(DHT)。内容包括不稳定性、瞬态和稳态要求等性能标准,以及控制不稳定性的方法。它甚至强调了验证数值代码的重要性。由于核反应堆使用耦合 SCFNCL 作为被动冷却系统,因此介绍了不同的拓扑结构和流体组合。有关耦合回路的实验研究报告非常有限,但进行了初步分析,结果表明了系统的有效性。综述还表明,有必要使用不同的超临界流体进行数值分析,并将其与核电厂系统和实验研究相结合,这可以与可再生能源和可持续能源的应用联系起来。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A comprehensive overview of advancements, applications, and impact of supercritical fluid natural circulation loops
Nowadays, many researches are persistently exploring to comprehend the various characteristic of the supercritical fluid natural circulation loop (SCFNCL) such as use of SCFNCL at normal operating condition as well as a passive system for heat removal from the core, steady state and transient behavior of the loop, heat transfer rate, heat transfer coefficient and optimizing mass flow rate of the loop. In last two decade, a significant research has been seen in the form of analytical, computational and experimental works which highlight the notable use of SCFNCL as an active and passive system in nuclear power plant (NPPs). However, very limited state of arts have been reported based on the loop geometry and their effects, different types of supercritical fluids (SCFs) and applications of the loops. Therefore, steady and transient behaviours of loop in single and parallel channels, thermal–hydraulic (TH) instability, effects of the geometrical and operating parameters on SCFNCL and deterioration of heat transfer (DHT) in SCFNCL are the main emphasis of this review. Performance criteria such as instability, transient, and steady-state requirements, along with methods for containing instability, have been covered. It even emphasizes how crucial it is to validate the numerical codes. Since nuclear reactors use coupled SCFNCL as passive cooling systems, different topologies and combinations of fluids are shown. Very limited experimental studies have been reported in the coupled loop, an initial analysis was conducted and the results demonstrated the effectiveness of the system. The review also demonstrated the need for numerical analysis with using different supercritical fluids and combine with the NPP systems as well as experimental investigations, which can be connected to applications in renewable and sustainable energy.
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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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