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A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104409] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Conservative analytical and experimental investigation of all pumps failure event in the primary cooling system for a 5 MWth research reactor. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2021.104041] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Wu P, Liu W, Gao C, Ma Y, Shan J. Preliminary safety evaluation of a supercritical carbon dioxide Brayton cycle cooled reactor system under loss-of-flow accident. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110860] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Yuan Y, Shan J, Zhang X, Wang L. Accident analysis of supercritical water reactors during startup. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2019.103227] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Guo X, Fan Y, Gao W, Tang R, Chen K, Shen Z, Zhang L. Corrosion resistance of candidate cladding materials for supercritical water reactor. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.12.007] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2018. [DOI: 10.1155/2018/6801736] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
Supercritical CO2 Brayton cycle is a good choice of thermal-to-electric energy conversion system, which owns a high cycle efficiency and a compact cycle configuration. It can be used in many power-generation applications, such as nuclear power, concentrated solar thermal, fossil fuel boilers, and shipboard propulsion system. Transient analysis code for Supercritical CO2 Brayton cycle is a necessity in the areas of transient analyses, control strategy study, and accident analyses. In this paper, a transient analysis code SCTRAN/CO2 is developed for Supercritical CO2 Brayton Loop based on a homogenous model. Heat conduction model, point neutron power model (which is developed for nuclear power application), turbomachinery model for gas turbine, compressor and shaft model, and PCHE type recuperator model are all included in this transient analysis code. The initial verifications were performed for components and constitutive models like heat transfer model, friction model, and compressor model. The verification of integrated system transient was also conducted through making comparison with experiment data of SCO2EP of KAIST. The comparison results show that SCTRAN/CO2 owns the ability to simulate transient process for S-CO2 Brayton cycle. SCTRAN/CO2 will become an important tool for further study of Supercritical CO2 Bryton cycle-based nuclear reactor concepts.
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Rowinski MK, Zhao J, White TJ, Soh YC. Safety analysis of Super-Critical Water Reactors–A review. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.03.002] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Development of safety analysis code for SCWR and its LOCA analysis of CSR1000. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2017.12.010] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Wu P, Yuan Y, Pan J, Shan J. The stability-analysis code FIAT development for density wave oscillations and its application to PV/PT SCWR. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.08.002] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Chen J, Zhou T, Chen J, Liu L, Muhammad AS, Muhammad ZA, Xia B. A calculation method for transient flow distribution of SCWR(CSR1000). ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.07.005] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Shahzad MA, Zhou T, Liu L. CSR1000 single channel thermal hydraulic stability analysis using response matrix method. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.04.007] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Liu L, Zhou T, Li Y, Chen J, Ali MZ, Xiao Z. SCWR transient safety analysis code SCAC-CSR1000. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.04.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.03.006] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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