W. Wiesenack, REVIEW OF HALDEN REACTOR PROJECT HIGH BURNUP FUEL DATA THAT CAN BE USED IN SAFETY ANALYSES, Nuclear Engineering and Design, 172(1-2), 1997, pp. 83-92
The fuels and materials testing programmes carried out at the OECD Hal
den Reactor Project are aimed at providing data in support of a mechan
istic understanding of phenomena, especially as related to high burnup
fuel. The investigations are focused on identifying long term propert
y changes, and irradiation techniques and instrumentation have been de
veloped over the years which enable to assess fuel behaviour and prope
rties in-pile. The examples presented include data on thermal and mech
anical behaviour, axial gas flow and pressure equilibration, fission g
as release, and fuel swelling and cladding creep. The in-pile measurem
ents can be used for understanding and modelling of phenomena such as
pellet-cladding mechanical interaction, fuel thermal conductivity degr
adation, a possible enhancement of fission gas release and cladding li
ft-off at high burnup. They do not only relate to fuel performance dur
ing normal operation, but can also be applied in safety analyses to de
fine the starting conditions of transients and to assess the further d
evelopments. (C) 1997 Elsevier Science S.A.