Optimization of inert matrix fuel concepts for americium transmutation
Concepts of inert-matrix fuels for americium are discussed. It is demonstrated that a 'hybrid' fuel design, consisting in a dispersion of an americium-bearing phase in an inert matrix, is desirable. More than solid-solution is preferred in order to localize within a small volume the damage in the matrix due to fission fragments.
Bibliographic Reference: Article: Journal of Nuclear Materials, 274 (1999), 105-111
Record Number: 199911559 / Last updated on: 1999-11-13
Original language: en
Available languages: en