Neutron moderation in inertial confinement fusion pellets and effects on damage and radioactive inventory
A standard time-dependent neutron transport computer code, TDA, is modified to allow time-varying material density to calculate the neutron spectrum from exploding inertial confinement fusion pellets with rho R values of 0 to 6 g/cm/sup 2/. Softening of the spectra due to neutron-fuel interactions causes a time-of-flight broadening of the neutron arrival time distribution at the chamber wall. It is found that the total number of displacements per atom (dpa) produced in a graphite first wall increases with the rho R of the pellet over the rho R range investigated because the dpa cross section is larger at lower neutron energy. However, the total helium production decreases with increasing rho R, as does the peak damage rate. Neutron-induced radioactivity generated in a 10-mg iron tamper is of the same magnitude as that produced in the rest of an entire reactor system.
- Research Organization:
- Univ. of Wisconsin, Madison
- OSTI ID:
- 5281207
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 47:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700208* -- Fusion Power Plant Technology-- Inertial Confinement Technology
CARBON
CONFINEMENT
CRYOGENIC FLUIDS
DEUTERIUM COMPOUNDS
DEUTERIUM TRITIDES
ELEMENTS
FIRST WALL
FLUIDS
FUEL PELLETS
FUELS
GAS PRODUCTION RATES
GRAPHITE
HELIUM
HYDROGEN COMPOUNDS
IMPLOSIONS
INERTIAL CONFINEMENT
LABELLED COMPOUNDS
MODERATORS
NEUTRON SLOWING-DOWN THEORY
NEUTRON SPECTRA
NONMETALS
PELLETS
PLASMA CONFINEMENT
RADIOACTIVITY
RARE GASES
SPECTRA
THERMONUCLEAR FUELS
THERMONUCLEAR IGNITION
THERMONUCLEAR REACTOR WALLS
TIME-OF-FLIGHT METHOD
TRITIUM COMPOUNDS