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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]
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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]
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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]
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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]
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5
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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]
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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]
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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]
Abstract
Abstract
Space fission power systems can enable ambitious solar-system and deep-space science missions. The heat pipe-cooled reactor is one of the most potential candidates for near-term space power supply, featuring safety, simplicity, reliability, and modularity. Heat pipe-cooled reactors are solid-state and high-temperature (up to 1500 K) reactors, where the thermal expansion is remarkable and the mechanical response significantly influences the neutronics and thermal analyses. Due to the considerable difference between heat pipe-cooled reactors and traditional water reactors in the structure and design concept, the coupling solutions for light water reactors cannot be directly applied to heat pipe-cooled reactor analyses. Therefore, a new coupling framework and program need to consider the coupling effects among neutronics, heat transfer, and mechanics. Based on the Monte Carlo program rmc and commercial finite element program ansysmechanicalansys parametric design language (APDL), this work introduces the three coupling fields of neutronics (N), thermal (T), and mechanics (M) for heat pipe cooled reactors. Besides, the finite element method and the Monte Carlo program use different meshes and geometry construction methods. Therefore, the spatial mapping and geometry reconstruction are also essential for the N/T-M coupling, which is discussed and established in detail. Furthermore, the N/T-M coupling methods are applied to the preliminary self-designed 10 kWel space heat pipe cooled reactor. Coupling shows that the thermal-mechanical feedback in the solid-state reactor has negative reactivity feedback (about −2000 pcm) while it has a deterioration in heat transfer due to the expansion in the gas gap.
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Affiliation(s)
- Yugao Ma
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China; Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
| | - Minyun Liu
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China
| | - Biheng Xie
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China
| | - Wenbin Han
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China
| | - Xiaoming Chai
- Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
| | - Shanfang Huang
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China
| | - Hongxing Yu
- Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
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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]
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9
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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]
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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]
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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]
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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]
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13
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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]
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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]
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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]
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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]
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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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