Published December 1996 | Version v1
Report Open

Investigation of fission products release and structural changes of WWER spent fuel in inert and oxidizing environment

  • 1. State Scientific Centre, Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation)

Description

At the Research Institute of Atomic Reactors in-cell experiments were carried out which were aimed at investigation of WWER spent fuel behaviour under accident conditions. Gaseous and volatile fission products release and the influence of gaseous swelling, fuel interaction with the cladding and oxidation on it have been investigated. At the present time, series of experiments in inert and air environments have been finished and the tests in steam environment have been carrying out. In all series the samples in the form of fuel pellets fragments and fuel elements pieces were used. This report presents some results of annealing tests and investigations of the sample microstructure after annealing. (author). 4 refs, 15 figs, 2 tabs

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Part of:
Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting
Imprint Pagination
299 p.
Journal Page Range
p. 79-99.
ISSN
1011-4289
Report number
IAEA-TECDOC--921

Conference

Title
Technical committee meeting on behaviour of LWR core materials under accident conditions.
Dates
9-13 Oct 1995.
Place
Dimitrovgrad (Russian Federation).

Optional Information