Benchmark experiments to simulate a nuclear transport flask loading accident with fuel elements of unequal reactivity
A series of measurements have been completed in the DIMPLE light water-moderated, low-power reactor to simulate a transport flask loading error. The experiments were designed with the aim of testing current calculational methods in extreme accident configurations. The programme was based on a 20 compartment boron-steel skip, used inside a steel container for pond storage of irradiated fuel from the UK Advanced Gas-Cooled Reactors. This in turn is placed inside a lead-lined steel flask for fuel transport. The reference loading for the sub-critical studies and the present accident simulation had identical arrays of 3% enriched uranium oxide pins loaded into each of the 20 skip compartments. To simulate a gross loading error, a cluster of 7% enriched uranium oxide pins replaced the lower enrichment pins in one of the compartments, firstly at the centre and then at the edge. The experiments established the critical water heights in each configuration. Measurements were also made of the U235 and U238 fission rate and the U238 capture rate distributions. The results of the measurements are compared with predictions using the MONK 6.3 and MORET Monte Carlo codes and the deterministic LWRWIMS-TWOTRAN code.
Bibliographic Reference: EUR 12048 EN (1989) 58 pp.
Record Number: 198910265 / Last updated on: 1994-12-01
Original language: en
Available languages: en