Preliminary calculations for testing a fission/fusion hybrid blanket module in a fission reactor: Addendum 1

Technical Report · Tue Dec 01 04:00:00 EST 1981

OSTI ID:5472472

Judd, J L

Calculations were performed with one-dimensional S/sub n/ transport theory to determine heating rates, tritium breeding, and fertile reaction rates of a fission/fusion hybrid blanket concept utilizing uranium as the fertile material. The results are compared with results of previous calculations using thorium as the fertile material. The calculations were done with ANISN using the EPR coupled 121-group (100n, 21..gamma..) cross section library and the MACKLIB-IV compilation of response functions. The heating rate profiles of the hybrid blanket containing thorium is similar to the profile calculated for a hybrid blanket containing uranium. The tritium breeding rate in the thorium case is 4% higher than the uranium case, while the fertile fission and capture rates are lower by 64 and 16%, respectively.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5472472
• Report Number(s): EGG-PHYS-5615(Add.1); ON: DE82010260
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING RATIO
CONVERSION RATIO
FUEL CYCLE
HEATING
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNETIC MIRROR TYPE REACTORS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
ONE-DIMENSIONAL CALCULATIONS
RADIATION HEATING
RADIOISOTOPES
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
THORIUM CYCLE
TMR REACTORS
TRANSPORT THEORY
TRITIUM
YEARS LIVING RADIOISOTOPES