Irradiation behavior of high uranium-density alloys in the plate fuels-Reference-Cited by-同舟云学术

Irradiation behavior of high uranium-density alloys in the plate fuels

Published:1998-03 Issue:1 Volume:254 Page:78-83
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ugajin M,Itoh A,Akabori M,Ooka N,Nakakura Y

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference10 articles.

1. Irradiation behavior of low-enriched U6Fe-Ai dispersion fuel elements

2. M. Ugajin, A. Itoh, M. Akabori, Preparation of U–Si/U–Me (Me=Fe, Ni, Mn) Al-dispersion plate type fuel (miniplates) for capsule irradiation, JAERI-M 93-121, June, 1993 (in Japanese).

3. M. Ugajin, Basic program to compute uranium density and void volume fraction in laboratory-scale uranium silicide aluminum dispersion plate-type fuel, JAERI-M 91-069, May, 1991.

4. M.J. Bell, ORIGEN – The ORNL Isotope Generation and Depletion Code, ORNL-4628, 1973.

5. Dynamics of irradiation-induced grain subdivision and swelling in U3Si2 and UO2 fuels

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