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Title: Preliminary evaluation of the /sup 233/U refresh cycle hybrid power system concept

Abstract

A preliminary evaluation was made of the technical feasibility of using a fusion reactor to breed /sup 233/U from thorium in high temperature gas cooled fission reactor fuel and then using this fuel in a fission reactor without reprocessing. Estimates of the neutronic performance of thorium fusion reactor blankets indicate that adequate concentration of /sup 233/U in thorium can be attained to allow operation of a high temperature gas cooled reactor using nonreprocessed fusion-bred /sup 233/U fuel. Estimates of the fuel materials damage indicate that the breeding and subsequent burning of /sup 233/U can be accomplished within the currently predicted materials limitations of high temperature gas-cooled reactor fuel. The system performance of this symbiotic fusion-fission power system, called the U-233 Refresh Cycle Hybrid Power System, was estimated. A refresh cycle fusion breeder reactor could support from two to three high temperature gas cooled fission burner reactors of equal thermal power without reprocessing. Greatly improved performance is possible if reprocessing is allowed. Thus preliminary evaluation shows that the concept is technically feasible and warrants more detailed study.

Authors:
; ; ; ; ; ; ;
Publication Date:
Research Org.:
General Atomic Co., San Diego, Calif. (USA)
OSTI Identifier:
7018241
Report Number(s):
GA-A-14940; CONF-780508-15
TRN: 78-015510
DOE Contract Number:  
EY-76-C-03-0167-038
Resource Type:
Conference
Resource Relation:
Conference: 3. meeting on the technology of controlled thermonuclear fusion, Santa Fe, NM, USA, 9 May 1978
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; HYBRID REACTORS; FUEL CYCLE; URANIUM 233; BREEDING; FEASIBILITY STUDIES; PERFORMANCE; THORIUM; THORIUM 232; THORIUM CYCLE; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; ELEMENTS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; HEAVY NUCLEI; ISOTOPES; METALS; NUCLEAR FUEL CONVERSION; NUCLEI; RADIOISOTOPES; THORIUM ISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES; 700205* - Fusion Power Plant Technology- Fuel, Heating, & Injection Systems

Citation Formats

Schultz, K R, Brogli, R H, Hopkins, G R, Bullock, R, Lund, K O, Wong, C, Bender, D J, and Lee, J D. Preliminary evaluation of the /sup 233/U refresh cycle hybrid power system concept. United States: N. p., 1978. Web.
Schultz, K R, Brogli, R H, Hopkins, G R, Bullock, R, Lund, K O, Wong, C, Bender, D J, & Lee, J D. Preliminary evaluation of the /sup 233/U refresh cycle hybrid power system concept. United States.
Schultz, K R, Brogli, R H, Hopkins, G R, Bullock, R, Lund, K O, Wong, C, Bender, D J, and Lee, J D. Sat . "Preliminary evaluation of the /sup 233/U refresh cycle hybrid power system concept". United States.
@article{osti_7018241,
title = {Preliminary evaluation of the /sup 233/U refresh cycle hybrid power system concept},
author = {Schultz, K R and Brogli, R H and Hopkins, G R and Bullock, R and Lund, K O and Wong, C and Bender, D J and Lee, J D},
abstractNote = {A preliminary evaluation was made of the technical feasibility of using a fusion reactor to breed /sup 233/U from thorium in high temperature gas cooled fission reactor fuel and then using this fuel in a fission reactor without reprocessing. Estimates of the neutronic performance of thorium fusion reactor blankets indicate that adequate concentration of /sup 233/U in thorium can be attained to allow operation of a high temperature gas cooled reactor using nonreprocessed fusion-bred /sup 233/U fuel. Estimates of the fuel materials damage indicate that the breeding and subsequent burning of /sup 233/U can be accomplished within the currently predicted materials limitations of high temperature gas-cooled reactor fuel. The system performance of this symbiotic fusion-fission power system, called the U-233 Refresh Cycle Hybrid Power System, was estimated. A refresh cycle fusion breeder reactor could support from two to three high temperature gas cooled fission burner reactors of equal thermal power without reprocessing. Greatly improved performance is possible if reprocessing is allowed. Thus preliminary evaluation shows that the concept is technically feasible and warrants more detailed study.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1978},
month = {4}
}

Conference:
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