The molten salt reactor (MSR) in generation IV: Overview and perspectives

被引:762
作者
Serp, Jerome [1 ]
Allibert, Michel [4 ]
Benes, Ondrej [2 ]
Delpech, Sylvie [3 ]
Feynberg, Olga
Ghetta, Veronique [4 ]
Heuer, Daniel [4 ]
Holcomb, David [5 ]
Ignatiev, Victor [6 ]
Kloosterman, Jan Leen [7 ]
Luzzi, Lelio [8 ]
Merle-Lucotte, Elsa [4 ]
Uhlir, Jan [9 ]
Yoshioka, Ritsuo [10 ]
Dai Zhimin [11 ]
机构
[1] CEA Marcoule, Radiochem & Proc Dept, Nucl Energy Div, SCPS LEPS, F-30207 Bagnols Sur Ceze, France
[2] Commiss European Communities, Joint Res Ctr, Inst Transuranium Elements, D-76125 Karlsruhe, Germany
[3] Univ Paris, IPNO, Grp Radiochim, F-91406 Orsay, France
[4] UJF Grenoble, INP, IN2P3 CNRS, LPSC, F-38026 Grenoble, France
[5] Oak Ridge Natl Lab, Oak Ridge, TN USA
[6] Kurchatov Inst, Natl Res Ctr, Moscow, Russia
[7] Delft Univ Technol, Dept Radiat Sci & Technol, NL-2629 JB Delft, Netherlands
[8] Politecn Milan, Dept Energy, Nucl Engn Div, I-20133 Milan, Italy
[9] Res Ctr Rez, CZ-25068 Rez, Czech Republic
[10] Int Thorium Molten Salt Forum, Tokyo, Japan
[11] Chinese Acad Sci, Shanghai 201800, Peoples R China
关键词
Molten salt reactor; Gen IV; Nuclear systems; Neutronic performance; Fuel cycle; FUEL-CYCLE; CORE PHYSICS; THORIUM; DESIGN;
D O I
10.1016/j.pnucene.2014.02.014
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Molten Salt Reactors (MSR) with the fuel dissolved in the liquid salt and fluoride-salt-cooled High-temperature Reactors (FHR) have many research themes in common. This paper gives an overview of the international R&D efforts on these reactor types carried out in the framework of Generation-IV. Many countries worldwide contribute to this reactor technology, among which the European Union, France, Japan, Russia and the USA, and for the past few years China and India have also contributed. In general, the international R&D focuses on three main lines of research. The USA focuses on the FHR, which will be a nearer-term application of liquid salt as a reactor coolant, while China also focuses on solid fuel reactors as a precursor to molten salt reactors with liquid fuel and a thermal neutron spectrum. The EU, France and Russia are focusing on the development of a fast spectrum molten salt reactor capable of either breeding or transmutation of actinides from spent nuclear fuel. Future research topics focus on liquid salt technology and materials behavior, the fuel and fuel cycle chemistry and modeling, and the numerical simulation and safety design aspects of the reactor. MSR development attracts more and more attention every year, because it is generally considered as most sustainable of the six Generation-IV designs with intrinsic safety features. Continuing joint efforts are needed to advance common molten salt reactor technologies. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:308 / 319
页数:12
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