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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