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Abstract

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.

Additional information

Authors: ITU KARLSRUHE, ITU KARLSRUHE, KARLSRUHE (DE);KARLSRUHE (DE), ITU KARLSRUHE, KARLSRUHE (DE)
Bibliographic Reference: Article: Journal of Nuclear Materials, 274 (1999), 105-111
Record Number: 199911559 / Last updated on: 1999-11-13
Category: PUBLICATION
Original language: en
Available languages: en
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