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For: Wu P, Gou J, Shan J, Zhang B, Li X. Preliminary safety evaluation for CSR1000 with passive safety system. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2013.11.031] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
Number Cited by Other Article(s)
1
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]
2
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]
3
Gaojian D, Qing L, Yu L, Danrong S, Dahuan Z. Large-break LOCA analysis of CSR1000. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108444] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
4
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]
5
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]
6
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]
7
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]
8
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]
9
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]
10
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]
11
Chen J, Zhou T, Liu L, Fang X. Analysis on LOCA for CSR1000. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.07.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
12
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]
13
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]
14
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]
15
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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