An online reprocessing facility for a one-fluid U-233/TH-232 flibe molten salt breeder reactor

American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV

Volumn 2, Issue , 2009, Pages 921-932

  Cramer, Chad M ^a   Shroy, Brent C ^b  

^a Battelle Memorial Institute ^*  (United States)

^b BATTELLE MEMORIAL INSTITUTE   (United States)

Author keywords

Breeder; Reprocessing; Salt; Thorium

Indexed keywords

BREEDER; CHEMCAD; CHEMICAL REPROCESSING; CHEMICAL SYSTEMS; COMMERCIAL ENERGY; COST-EFFICIENT; FUEL CYCLE; FUEL RECYCLING; FULLY INTEGRATED; MOLTEN SALT BREEDER REACTORS; MOLTEN SALT REACTOR; MULTIPLE COMPUTERS; PROCESS DEVELOPMENT; PROLIFERATION CONCERN; REACTOR PLANTS; REPROCESSING; REPROCESSING FACILITIES; SEPARATION TECHNIQUES; THORIUM REACTOR;

BREEDER REACTORS; COMPUTER SIMULATION; FUELS; FUSED SALTS; MOLTEN MATERIALS; NUCLEAR ENERGY; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; NUCLEAR PROPULSION; REACTOR SHUTDOWNS; THORIUM;

NUCLEAR FUEL REPROCESSING;

EID: 74549145135     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (7)

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2. E.S. Bettis, et al., "The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor," Oak Ridge National Laboratory, Nuclear Applications & Technology, 8, 190, 1970.
3. D. Scott, et al., "Graphite and Xenon Behavior and Their Influence on Molten-Salt Reactor Design," Nuclear Applications & Technology, 8, 179, 1970.
4. Blanco, RE, et al. "Aqueous Processing of Thorium Fuels, Part II," ORNL-3418, June 1963.
5. Benedict, Pigford and Levi, Nuclear Chemical Engineering, Second Edition, McGraw Hill, 1981.
6. Barton, CJ and HH Stone, "Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures," Oak Ridge National Laboratory, ORNL-TM-1543, 1966.
7. Reddick, GW. "Solvent Extraction in HTGR Reprocessing," Interim Development Report GA-A13835," February 1976.