Parametric studies on the neutronics of a hybrid (fusion-fission) blanket

Conference · Mon Jul 01 04:00:00 EDT 1985 · Fusion Technol.; (United States)

OSTI ID:6010849

Sedano, P G; Perlado, J M

Several neutronic calculations have been made for a specific hybrid blanket design in order to evaluate the capability that a fissile zone offers to improve the tritium or fissile fuel production and the energy gain of a fusion blanket. Studies with different fissile zone thickness show the usefulness of thin fissle zones to get high tritium breeding rates. Better total material (tritium plus fissile) production requires thicker fissile zones. Comparisons have been made between the materials neutronic damage expected in a pure fusion blanket and in a hybrid one, with greater energy to damage ratios obtained for the hybrid. Also, greater energy and damage rates are obtained for harder spectra (more 14 MeV neutrons in source) because of the higher potential of 14 MeV neutrons to produce fission in the hybrid blanket.

• Research Organization: Dpto. Energia Nuclear, ETSI Industriales (U.P.M.), Castellana
• OSTI ID: 6010849
• Report Number(s): CONF-850310-
• Conference Information: Journal Name: Fusion Technol.; (United States) Journal Volume: 8:1
• 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 BLANKETS
BREEDING RATIO
COMPARATIVE EVALUATIONS
CONVERSION RATIO
DAMAGING NEUTRON FLUENCE
DIMENSIONS
FISSILE MATERIALS
FISSION YIELD
FISSIONABLE MATERIALS
FUSION YIELD
HYBRID REACTORS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS
NEUTRON FLUENCE
NEUTRON FLUX
NUCLEAR REACTION YIELD
NUCLEI
ODD-EVEN NUCLEI
PARAMETRIC ANALYSIS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIATION FLUX
RADIOISOTOPES
REACTOR COMPONENTS
THICKNESS
TRITIUM
YEARS LIVING RADIOISOTOPES
YIELDS