Application of the passive turbocharger to PRHRS in integral PWR type SMR with an sCO2 power cycle

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-25 DOI:10.1016/j.anucene.2024.110874
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Abstract

One of the potential design concepts for small modular reactor(SMR) is coupling an integral pressurized water reactor(IPWR) with a supercritical CO2(sCO2) power cycle to reduce the plant footprint. However, the passive safety systems of this SMR concept have not been well established compared to steam power cycle based SMRs. In this study, a passive turbocharger utilizing the unique characteristics of sCO2 is proposed as a way to improve the passive safety of sCO2 power cycle. This is the concept of installing a turbine-compressor set at the connection of passive residual heat removal system(PRHRS) to effectively remove the high level of residual heat in the early stages of an accident rather than relying only on natural circulation cooling. Based on the findings, it can be concluded that proposed sCO2 turbocharger concept has the potential to enhance performance of PRHRS and reduce the height of natural circulation loop leading to smaller volume.

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将被动式涡轮增压器应用于具有 sCO2 功率循环的整体式压水堆型 SMR 中的 PRHRS
小型模块化反应堆(SMR)的潜在设计概念之一是将整体压水堆(IPWR)与超临界二氧化碳(sCO2)动力循环相结合,以减少电厂占地面积。然而,与基于蒸汽动力循环的 SMR 相比,这种 SMR 概念的被动安全系统尚未完善。在本研究中,我们提出了一种利用二氧化碳独特特性的被动式涡轮增压器,以此来提高二氧化碳动力循环的被动安全性。这一概念是在被动余热排除系统(PRHRS)的连接处安装一套涡轮压缩机组,以便在事故早期有效地排除大量余热,而不是仅仅依靠自然循环冷却。根据研究结果,可以得出结论,拟议的 sCO2 涡轮增压器概念有可能提高被动余热排除系统的性能,并降低自然循环回路的高度,从而缩小体积。
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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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