Published April 1993 | Version v1
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Fission gas release and fuel rod chemistry related to extended burnup

Description

The purpose of the meeting was to review the state of the art in fission gas release and fuel rod chemistry related to extended burnup. The meeting was held in a time when national and international programmes on water reactor fuel irradiated in experimental reactors were still ongoing or had reached their conclusion, and when lead test assemblies had reached high burnup in power reactors and been examined. At the same time, several out-of-pile experiments on high burnup fuel or with simulated fuel were being carried out. As a result, significant progress has been registered since the last meeting, particularly in the evaluation of fuel temperature, the degradation of the global thermal conductivity with burnup and in the understanding of the impact on fission gas release. Fifty five participants from 16 countries and one international organization attended the meeting. 28 papers were presented. A separate abstract was prepared for each of the papers. Refs, figs, tabs and photos

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Subtitle (English)
Proceedings of a technical committee meeting held in Pembroke, Ontario, Canada, 28 April - 1 May 1992

Publishing Information

Imprint Pagination
235 p.
ISSN
1011-4289
Report number
IAEA-TECDOC--697

Conference

Title
Technical committee meeting on fission gas release and fuel rod chemistry related to extended burnup.
Dates
28 Apr - 1 May 1992.
Place
Pembroke, ON (Canada).