Research on the passive residual heat removal capacity of supercritical carbon dioxide

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-09-16 DOI:10.1016/j.nucengdes.2024.113592
Gonghao Lu , Guangxu Zhang , Chao Jin , Jiajun Tang , Rongshun Xie , Gang Hong , Yaoli Zhang
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Abstract

To investigate the passive residual heat removal capacity of supercritical carbon dioxide (S-CO2), this study takes a 12MWe lead–bismuth fast reactor as an example and analyzes two indirect S-CO2 passive residual heat removal system (PRHRS) designs (design 1 based on steam generator (SG) and design 2 based on independent heat exchanger (IHEX)). One-dimensional modeling was conducted using the Modelica language, and detailed analysis was performed on important components. The passive residual heat removal capacity of S-CO2 was evaluated through simulation calculations. The research results show that the maximum temperature of relevant design based on SG and IHEX does not exceed the pipeline design basis. Both design can reasonably and effectively remove the residual heat from the reactor core. The original equipment of the S-CO2 Brayton recompression cycle can be directly used to remove residual heat without compromising the relatively simple arrangement. The reasons for the occurrence of peak flow rate are discussed. Meanwhile, an analysis of the outlet temperature of the loop under different pressures in the SG design concludes that the operating pressure of the scheme should exceed 8.5 MPa.

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超临界二氧化碳被动余热去除能力研究
为了研究超临界二氧化碳(S-CO2)的被动余热去除能力,本研究以 12MWe 铅铋快堆为例,分析了两种间接 S-CO2 被动余热去除系统(PRHRS)设计(基于蒸汽发生器(SG)的设计 1 和基于独立热交换器(IHEX)的设计 2)。使用 Modelica 语言进行了一维建模,并对重要组件进行了详细分析。通过模拟计算评估了 S-CO2 的被动余热去除能力。研究结果表明,基于 SG 和 IHEX 的相关设计的最高温度不会超过管道设计基准。两种设计都能合理有效地去除反应堆堆芯的余热。S-CO2 布雷顿再压缩循环的原有设备可直接用于去除余热,而不会影响相对简单的布置。讨论了出现峰值流速的原因。同时,通过分析 SG 设计中不同压力下的回路出口温度,得出结论认为该方案的运行压力应超过 8.5 兆帕。
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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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