Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling

Technical Report · Tue Jul 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5352526· OSTI ID:5352526

Engel, J R; Bauman, H F; Dearing, J F; Grimes, W R; McCoy, H E; Rhoades, W A

A study was made to examine the conceptual feasibility of a molten-salt power reactor fueled with denatured /sup 235/U and operated with a minimum of chemical processing. Because such a reactor would not have a positive breeding gain, reductions in the fuel conversion ratio were allowed in the design to achieve other potentially favorable characteristics for the reactor. A conceptual core design was developed in which the power density was low enough to allow a 30-year life expectancy of the moderator graphite with a fluence limit of 3 x 10/sup 26/ neutrons/m/sup 2/ (E > 50 keV). This reactor could be made critical with about 3450 kg of 20% enriched /sup 235/U and operated for 30 years with routine additions of denatured /sup 235/U and no chemical processing for removal of fission products. A review of the chemical considerations assoicated with the conceptual fuel cycle indicates that no substantial difficulties would be expected if the soluble fission products and higher actinides were allowed to remain in the fuel salt for the life of the plant.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5352526
• Report Number(s): ORNL/TM-7207
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GRAPHITE MODERATED REACTORS
FEASIBILITY STUDIES
SPECIFICATIONS
MOLTEN SALT COOLED REACTORS
MOLTEN SALT FUELED REACTORS
DENATURED FUEL
FUEL CYCLE
REACTOR KINETICS
REACTOR MATERIALS
ENERGY SOURCES
FLUID FUELED REACTORS
FUELS
KINETICS
MATERIALS
MOLTEN SALT REACTORS
NUCLEAR FUELS
REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated