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Title: Concept evaluation of nuclear fusion driven symbiotic energy systems

Concept evaluation of nuclear fusion driven symbiotic energy systems 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:
OSTI Identifier:5466590
Report Number(s):CONF-791204-34
TRN: 80-009250
DOE Contract Number:W-7405-ENG-26
Resource Type:Conference
Data Type:
Resource Relation:Conference: 2. Miami international conference on alternative energy sources, Miami Beach, FL, USA, 10 Dec 1979
Research Org:Oak Ridge National Lab., TN (USA)
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