Published August 1997 | Version v1
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Fission gas release during post irradiation annealing of large grain size fuels from Hinkley point B

Creators

  • 1. Nuclear Electric plc, Barnwood (United Kingdom)

Description

A series of post-irradiation anneals has been carried out on fuel taken from an experimental stringer from Hinkley Point B AGR. The stringer was part of an experimental programme in the reactor to study the effect of large grain size fuel. Three differing fuel types were present in separate pins in the stringer. One variant of large grain size fuel had been prepared by using an MgO dopant during fuel manufactured, a second by high temperature sintering of standard fuel and the third was a reference, 12μm grain size fuel. Both large grain size variants had similar grain sizes around 35μm. The present experiments took fuel samples from highly rated pins from the stringer with local burn-up in excess of 25GWd/tU and annealed these to temperature of up to 1535 deg. C under reducing conditions to allow a comparison of fission gas behaviour at high release levels. The results demonstrate the beneficial effect of large grain size on release rate of 85Kr following interlinkage. At low temperatures and release rates there was no difference between the fuel types, but at temperatures in excess of 1400 deg. C the release rate was found to be inversely dependent on the fuel grain size. The experiments showed some differences between the doped and undoped large grains size fuel in that the former became interlinked at a lower temperature, releasing fission gas at an increased rate at this temperature. At higher temperatures the grain size effect was dominant. The temperature dependence for fission gas release was determined over a narrow range of temperature and found to be similar for all three types and for both pre-interlinkage and post-interlinkage releases, the difference between the release rates is then seen to be controlled by grain size. (author). 4 refs, 7 figs, 3 tabs

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Part of:
Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting
Imprint Pagination
559 p.
Journal Page Range
p. 467-479.
ISSN
1011-4289
Report number
IAEA-TECDOC--957

Conference

Title
Technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support.
Dates
19-23 Sep 1994.
Place
Windermere (United Kingdom).

Optional Information