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

Abstract

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.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
5352526
Report Number(s):
ORNL/TM-7207
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Engel, J.R., Bauman, H.F., Dearing, J.F., Grimes, W.R., McCoy, H.E., and Rhoades, W.A. Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling. United States: N. p., 1980. Web. doi:10.2172/5352526.
Engel, J.R., Bauman, H.F., Dearing, J.F., Grimes, W.R., McCoy, H.E., & Rhoades, W.A. Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling. United States. doi:10.2172/5352526.
Engel, J.R., Bauman, H.F., Dearing, J.F., Grimes, W.R., McCoy, H.E., and Rhoades, W.A. Tue . "Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling". United States. doi:10.2172/5352526. https://www.osti.gov/servlets/purl/5352526.
@article{osti_5352526,
title = {Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling},
author = {Engel, J.R. and Bauman, H.F. and Dearing, J.F. and Grimes, W.R. and McCoy, H.E. and Rhoades, W.A.},
abstractNote = {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.},
doi = {10.2172/5352526},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jul 01 00:00:00 EDT 1980},
month = {Tue Jul 01 00:00:00 EDT 1980}
}

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