Helium release from the uranium–plutonium mixed oxide (MOX) fuel irradiated to high burn-up in a fast breeder reactor (FBR)

Author:

Katsuyama Kozo,Ishimi Akihiro,Maeda Koji,Nagamine Tsuyoshi,Asaga Takeo

Publisher

Elsevier BV

Subject

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

Reference12 articles.

1. H. Bairiot, M. Lippens, Commercial MOX fuel: the experimental and demonstration background, in: Technical Committee Meeting Recycling of Pu and U in Water Reactor Fuel, Cadarache, France, 13–16 November 1989.

2. The behaviour of helium in UO2: Solution and migration energies

3. M. Billaux, M. Lippenns, D. Boulanger, Proceedings of a Conference on Water Reactor Fuel Element Computer Modelling in Steady State, Transient and Accident Conditions, Preston, UK, 18–22 September 1988, pp. 182–186.

4. T. Mitsugi, N. Kushida, K. Kikuchi, 1997 International Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon, 2–6 March 1997, pp. 54–61.

5. Diffusion of radiogenic helium in natural uranium oxides

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