ALLEGRO氦冷快堆衰变排热系统的研究

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Zsombor Bali , Gusztáv Mayer
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引用次数: 0

摘要

ALLEGRO是21世纪初第四代国际论坛(Generation IV International Forum, GIF)选择用于未来研究的GFR2400氦冷气体快堆的示范反应堆。在过去的二十年里,这个75兆瓦的热电示范反应堆已经在几个欧洲项目中开发出来。目前ALLEGRO的设计包括主热交换器(MHX)和衰变热去除系统(DHR)的二次侧的加压水。然而,在mhx或dhr发生一次-二次断裂的情况下,水冷剂可能会进入气冷堆芯,这可能会导致反应性和腐蚀问题。因此,替换mhx和dhr中的二次水是ALLEGRO设计阶段的一个重要课题。本文利用CATHARE热工液压系统程序,研究了不同压力下,氦、氮和CO2作为dhr二次冷却剂的可能性。结果表明,从冷却性能的角度来看,CO2气体是一种很有前途的候选气体,并且通过使用该气体,在DHR换热器的尺寸方面需要相对较小的设计变化。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Investigation of decay heat removal systems in the ALLEGRO helium-cooled fast reactor
ALLEGRO is a demonstrator reactor of the GFR2400 helium-cooled gas fast reactor selected for future research by the Generation IV International Forum (GIF) in the early 2000s. This 75 MW thermal power demonstrator reactor has been developed in several European projects over the past two decades. The current ALLEGRO design consists of pressurized water on the secondary side of both the main heat exchangers (MHX) and the decay heat removal systems (DHR). Nevertheless, in case of a primary-secondary break at the MHXs or the DHRs, the water coolant may ingress into the gas-cooled reactor core which may cause reactivity and corrosion issues. For this reason, replacing the secondary water in the MHXs and the DHRs is an important topic during the design phase of ALLEGRO. In this paper, the gases of helium, nitrogen and CO2 are investigated as possible secondary coolants of the DHRs at different pressures using the CATHARE thermal hydraulics system code. The results show that from a cooling performance point of view, CO2 gas is a promising candidate and by using this gas, a relatively small design change is needed concerning the size of the DHR heat exchangers.
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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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