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This set contains the experimental data from the OECD Halden Reactor Project made available for the FUMEX-I exercise (Fuel Modelling at Extended Burnup) carried out under the auspices of the IAEA.
The six cases are:
FUMEX 1:This data set represents the irradiation of production line PWR type fuel under benign conditions. Temperatures remained low but increased slightly with burnup.
FUMEX 2:This was a small diameter rod designed to achieve rapid accumulation of burnup. Temperatures were estimated to remain low. The internal pin pressure was measured in-pile and an assessment of FGR was also provided by PIE.
FUMEX 3: This case consisted of 3 short rods equipped with centreline thermocouples each with a different gap and fill gas composition. After steady state irradiation to ~30 MW.d/kg UO2, they were given a severe increase in power (power ramp).
FUMEX 4: Two rods filled with 3 bar He and 1 bar He/Xe mixture were irradiated to ~33 MW.d/kg UO2. Both rods experienced a period of increased power part way through the irradiation.
FUMEX 5: The test case comprised a single rod base irradiated at low power to 16 MW.d/kg UO2 with a power ramp and a hold period at the end of life. The main purpose of this case was to assess pellet clad mechanical interaction (PCMI) and fission gas release (FGR) under ramp conditions.
FUMEX 6: Two rods were base irradiated at low power. The rods were refabricated to include pressure transducers. Rod internal pressure was monitored during power ramps, one fast, one slow.
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Keywords: burnup, cladding, creep, fission gas release, fuel behaviour, post-irradiation examination, power ramp, pwr reactors.