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Abstract
According to the most recently revised European design strategy for DEMO breeding blankets, mature concepts have been identified that require a reduced technological extrapolation towards DEMO and will be tested in ITER. In order to optimize and finalize the design of test blanket modules, a number of issues have to be better understood that are related to the magnetohydrodynamic (MHD) interactions of the liquid breeder with the strong magnetic field that confines the fusion plasma. The aim of the present paper is to describe the state of the art of the study of MHD effects coupled with other physical phenomena, such as tritium transport, corrosion and heat transfer. Both numerical and experimental approaches are discussed, as well as future requirements to achieve a reliable prediction of these processes in liquid metal blankets.
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Atchutuni SS, Agravat HS, Chauhan J, E. RK. Corrosion behavior of IN-RAFM steel with stagnant lead-lithium at 550 °C up to 9000 h. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.07.015] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Affiliation(s)
- Shaoqiu Huang
- Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Key Laboratory of Neutronics and Radiation, Hefei, Anhui 230031, China
- University of Science and Technology of China, Hefei, Anhui 230027, China
| | - Zhiqiang Zhu
- Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Key Laboratory of Neutronics and Radiation, Hefei, Anhui 230031, China
| | - Wangli Huang
- Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Key Laboratory of Neutronics and Radiation, Hefei, Anhui 230031, China
| | - Jian He
- Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Key Laboratory of Neutronics and Radiation, Hefei, Anhui 230031, China
| | - Jie Yu
- Chinese Academy of Sciences, Institute of Nuclear Energy Safety Technology, Key Laboratory of Neutronics and Radiation, Hefei, Anhui 230031, China
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Chakraborty P, Kain V, Tewari R, Dey GK. Corrosion of an India produced RAFM steel in flowing lead-lithium eutectic. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.08.010] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Gu Z, Wang G, Wang Z, Song Y, Zhao Z. Safety analyses of 10 MW th Forced Circulation LBE-cooled Fast Reactor during unprotected transients. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.11.004] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Wu Y, Bai Y, Song Y, Huang Q, Zhao Z, Hu L. Development strategy and conceptual design of China Lead-based Research Reactor. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.08.015] [Citation(s) in RCA: 112] [Impact Index Per Article: 14.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Xu J, Wang D, Wang J, Wang J, Hu L. Preliminary Quantitative Evaluation of Potential Risk for HCCB TBS Tritium Extraction System Based on Fault Tree Analysis. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9972-x] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Zhao Y, Zhai X, Liu S, Li C, Huang Q. High cycle fatigue properties of CLAM steel at 723 K and 823 K. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.08.010] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Kinematics analysis and verification of In-Vessel Fuel Handling System for China Lead-based Research Reactor. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.05.031] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Bühler L, Mistrangelo C, Konys J, Bhattacharyay R, Huang Q, Obukhov D, Smolentsev S, Utili M. Facilities, testing program and modeling needs for studying liquid metal magnetohydrodynamic flows in fusion blankets. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2014.03.078] [Citation(s) in RCA: 24] [Impact Index Per Article: 2.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Effect of post-weld heat treatment on the mechanical properties of CLAM/316L dissimilar joint. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.06.194] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Spectrum Analyses and Diagnoses of 350 kV HVPS Ripples on High Intensity D–T Fusion Neutron Generator. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9909-4] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Shen L, Zhai X, Chen C, Li C, Wang F. A Preliminary Study on the CLAM Steel Composition Optimization Based on Extreme Learning Machine. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9912-9] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Fuel cladding integrity analysis during beam trip transients for China lead-based demonstration reactor. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.03.028] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Wang W, Song Y, Wang J, Wang Y, Song G. Design of the 2.45 GHz ECR Ion Source Control System for High Intensity D–T Fusion Neutron Generator. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9853-3] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Zhai Y, Li C, Huang B, Huang Q, Zhang J. Effect of Electron Beam Currents on Welding Quality of CLAM Steel for High Density Cooling Channels. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9871-1] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Experimental Studies of MHD Pressure Drop of PbLi Flow in Rectangular Pipes Under Uniform Magnetic Field. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9848-0] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Preliminary Shielding Design and Analysis of Liquid Lead–Lithium Blanket for Chinese Fusion Engineering Testing Reactor. JOURNAL OF FUSION ENERGY 2014. [DOI: 10.1007/s10894-014-9819-x] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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