Preliminary calculations for testing a fission/fusion hybrid blanket module in a fission reactor: addendum II
Technical Report
·
OSTI ID:5154213
Neutronic calculations are performed for a fission/fusion hybrid blanket module in a fission reactor to compare the performance of the module with a uranium-238 blanket in a fission environment versus a fusion environment. The analysis is based on placing a first wall/blanket module. The Tandem Mirror Hybrid Reactor (TMHR) Benchmark Design, in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory. Heating rates, tritium breeding, and reaction rates are computed for the uranium-238 hybrid module located on one side of the ETR core. The calculations are performed with one-dimensional S/sub n/ transport theory using ANISN and a coupled 121-group (100n,21..gamma..) library. The results are compared with the rates for the hybrid blanket module in a fusion environment. The total heating and tritium breeding rates of the hybrid blanket are greater in ETR operating at 175 MW than in the TMHR at a 1 MW/m/sup 2/ wall loading. However, the uranium-238 capture and fission rates are lower in the ETR environment by factors of 1.6 and 7.4, respectively.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5154213
- Report Number(s):
- EGG-PHYS-5615-Add.2; ON: DE82015622
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
EVEN-EVEN NUCLEI
FIRST WALL
FISSION
HADRON REACTIONS
HEAVY NUCLEI
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
PERFORMANCE TESTING
POWER DENSITY
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
TESTING
THERMONUCLEAR REACTOR WALLS
TRANSPORT THEORY
TRITIUM
URANIUM 238
URANIUM ISOTOPES
WALL LOADING
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
EVEN-EVEN NUCLEI
FIRST WALL
FISSION
HADRON REACTIONS
HEAVY NUCLEI
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
PERFORMANCE TESTING
POWER DENSITY
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
TESTING
THERMONUCLEAR REACTOR WALLS
TRANSPORT THEORY
TRITIUM
URANIUM 238
URANIUM ISOTOPES
WALL LOADING
YEARS LIVING RADIOISOTOPES