Evaluation of Salt Coolants for Reactor Applications

Abstract Molten fluorides were initially developed for use in the nuclear industry as the high-temperature fluid fuel for the Molten Salt Reactor (MSR). The U.S. Department of Energy Office of Nuclear Energy is exploring the use of molten salts as primary and secondary coolants in a new generation of solid-fueled, thermal-spectrum, high-temperature reactors. This paper provides a review of relevant properties for use in evaluation and ranking of salt coolants for high-temperature reactors. Nuclear, physical, and chemical properties were reviewed, and metrics for evaluation are recommended. Chemical properties of the salt were examined to identify factors that affect materials compatibility (i.e., corrosion). Some preliminary consideration of economic factors for the candidate salts is also presented.

[1]  Neil E. Todreas,et al.  Flexible Conversion Ratio Fast Reactor Systems Evaluation , 2008 .

[2]  D. Williams,et al.  Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) , 2006 .

[3]  Kenneth D. Kok,et al.  Nuclear engineering handbook , 2009 .

[4]  H. McCoy,et al.  Status of materials development for molten salt reactors , 1978 .

[5]  Redox Potential of Novel Electrochemical Buffers Useful for Corrosion Prevention in Molten Fluorides , 2002 .

[6]  Paul J. Turinsky,et al.  NESTLE. Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method , 1994 .

[7]  R. W. Mar,et al.  Industrial use of molten nitrate/nitrite salts , 1981 .

[8]  Dusan Lexa,et al.  Preparation and physical characteristics of a lithium-beryllium-substituted fluorapatite , 1999 .

[9]  P. Peterson,et al.  Molten-Salt-Cooled Advanced High-Temperature Reactor for Production of Hydrogen and Electricity , 2003 .

[10]  W. R. Grimes.  CHEMICAL RESEARCH AND DEVELOPMENT FOR MOLTEN-SALT BREEDER REACTORS. , 1967 .

[11]  H. W. Hoffman.  MOLTEN SALT HEAT TRANSFER , 1958 .

[12]  W. R. Grimes.  Molten-Salt Reactor Chemistry , 1970 .

[13]  Bucholz,et al.  SCALE: a modular code system for performing standardized computer analyses for licensing evaluation , 1981 .

[14]  D. Williams,et al.  Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop , 2006 .

[15]  Dt Ingersoll,et al.  Status of Physics and Safety Analyses for the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) , 2005 .