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Title: Concept evaluation of nuclear fusion driven symbiotic energy systems

Abstract

This paper analyzes systems based on D-T and semi-catalyzed D-D fusion-powered U233 breeders. Two different blanket types were used: metallic thorium pebble-bed blankets with a batch reprocessing mode and a molten salt blanket with on-line continuous or batch reprocessing. All fusion-driven blankets are assumed to have spherical geometries, with a 85% closure. Neutronics depletion calculations were performed with a revised version of the discrete ordinates code XSDRN-PM, using multigroup (100 neutron, 21 gamma-ray groups) coupled cross-section libraries. These neutronics calculations are coupled with a scenario optimization and cost analysis code. Also, the fusion burn was shaped so as to keep the blanket maximum power density below a preset value, and to improve the performance of the fusion-driven systems. The fusion-driven symbiotes are compared with LMFBR-driven energy systems. The nuclear fission breeders that were used as drivers have parameters characteristic of heterogeneous, oxide LMFBRs. They are net plutonium users - the plutonium is obtained from the discharges of LWRs - and U233 is bred in the fission breeder thorium blankets. The analyses of the symbiotic energy systems were performed at equilibrium, at maximum rate of grid expansion, and for a given nuclear power demand.

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
5466590
Report Number(s):
CONF-791204-34
TRN: 80-009250
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Conference
Resource Relation:
Conference: 2. Miami international conference on alternative energy sources, Miami Beach, FL, USA, 10 Dec 1979
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HYBRID REACTORS; FUEL CYCLE; LMFBR TYPE REACTORS; BREEDING; BREEDING BLANKETS; COMPARATIVE EVALUATIONS; COST; DEUTERIUM; DISCRETE ORDINATE METHOD; ECONOMIC ANALYSIS; MOLTEN SALTS; NEUTRON TRANSPORT; PROLIFERATION; THORIUM CYCLE; TRITIUM; URANIUM 233; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BREEDER REACTORS; ECONOMICS; EPITHERMAL REACTORS; EVEN-ODD NUCLEI; FAST REACTORS; FBR TYPE REACTORS; HEAVY NUCLEI; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LIQUID METAL COOLED REACTORS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUEL CONVERSION; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SALTS; STABLE ISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES; 700205* - Fusion Power Plant Technology- Fuel, Heating, & Injection Systems; 210802 - Nuclear Power Plants- Economics- Fuel Cycle

Citation Formats

Renier, J. P., and Hoffman, T. J. Concept evaluation of nuclear fusion driven symbiotic energy systems. United States: N. p., 1979. Web.
Renier, J. P., & Hoffman, T. J. Concept evaluation of nuclear fusion driven symbiotic energy systems. United States.
Renier, J. P., and Hoffman, T. J. Mon . "Concept evaluation of nuclear fusion driven symbiotic energy systems". United States. https://www.osti.gov/servlets/purl/5466590.
@article{osti_5466590,
title = {Concept evaluation of nuclear fusion driven symbiotic energy systems},
author = {Renier, J. P. and Hoffman, T. J.},
abstractNote = {This paper analyzes systems based on D-T and semi-catalyzed D-D fusion-powered U233 breeders. Two different blanket types were used: metallic thorium pebble-bed blankets with a batch reprocessing mode and a molten salt blanket with on-line continuous or batch reprocessing. All fusion-driven blankets are assumed to have spherical geometries, with a 85% closure. Neutronics depletion calculations were performed with a revised version of the discrete ordinates code XSDRN-PM, using multigroup (100 neutron, 21 gamma-ray groups) coupled cross-section libraries. These neutronics calculations are coupled with a scenario optimization and cost analysis code. Also, the fusion burn was shaped so as to keep the blanket maximum power density below a preset value, and to improve the performance of the fusion-driven systems. The fusion-driven symbiotes are compared with LMFBR-driven energy systems. The nuclear fission breeders that were used as drivers have parameters characteristic of heterogeneous, oxide LMFBRs. They are net plutonium users - the plutonium is obtained from the discharges of LWRs - and U233 is bred in the fission breeder thorium blankets. The analyses of the symbiotic energy systems were performed at equilibrium, at maximum rate of grid expansion, and for a given nuclear power demand.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {1}
}

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