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For: Ma Y, Chen E, Yu H, Zhong R, Deng J, Chai X, Huang S, Ding S, Zhang Z. Heat pipe failure accident analysis in megawatt heat pipe cooled reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107755] [Citation(s) in RCA: 18] [Impact Index Per Article: 3.6] [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
Insights in the safety analysis of an early microreactor design. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112203] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/06/2023]
2
Guo Y, Su Z, Li Z, Yu J, Wang K. Research on the effect of heat pipe temperature oscillation on heat pipe cooled reactor operation. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109587] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
3
Liu S, Kang M, Yuan Y, Huang Q, Du Z, He X, Zhou Y. Experimental study of explosion characteristics caused by High-Temperature sodium leakage from a heat pipe into air. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109387] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
4
Startup analyses of a megawatt heat pipe cooled reactor. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104405] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
5
Failure probability evaluation for a weld of the heat pipe in the Mega-Power heat pipe cooled reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109324] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
6
Chen S, Cai B, Yuan C, Li Z, Zhang C. Evaluation of neutron irradiation-induced displacement damage in heat pipe reactor. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101216] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
7
Ma Y, Liu M, Xie B, Han W, Chai X, Huang S, Yu H. Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2022. [DOI: 10.1115/1.4051612] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
8
Huang J, Wang C, Guo K, Zhang D, Su G, Tian W, Qiu S. Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111652] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
9
Ma K, Hu P. Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108907] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
10
Feng K, Wu Y, Hu J, Jin X, Gu H, Guo H. Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2021.111622] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
11
Ma Y, Liu J, Yu H, Tian C, Huang S, Deng J, Chai X, Liu Y, He X. Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.01.002] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
12
Ma Y, Han W, Xie B, Yu H, Liu M, He X, Huang S, Liu Y, Chai X. Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111473] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
13
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111404] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
14
Ma Y, Tian C, Yu H, Zhong R, Zhang Z, Huang S, Deng J, Chai X, Yang Y. Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103904] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
15
Tian Z, Wang C, Huang J, Guo K, Zhang D, Liu X, Su G, Tian W, Qiu S. Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108396] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
16
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111182] [Citation(s) in RCA: 13] [Impact Index Per Article: 3.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
17
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107923] [Citation(s) in RCA: 16] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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