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Neutron moderation in inertial confinement fusion pellets and effects on damage and radioactive inventory

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5281207

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