A neutron coincidence counter, SMP-D4 installed at the Sellafield Mox Plant (SMP) for the verification of the flow of MOX fuel pins during production, has been fully modelled using the Monte Carlo codes, MCNP-PTA, which simulate both the neutron transport and the coincidence electronics. The model has been validated using measurements carried out on site with Mixed Oxide (MOX) fuel pins and the efficiency of the counter for 252Cf radionuclide neutron source spectrum has also been calculated. Both types of measurements agreed extremely well with our calculations. A user interface has been developed to allow an inspector, on site, to define the loading pattern of the magazine, prepare the input file to MCNP PTA and run the Monte Carlo simulation code for a given pre-declared loading pattern. One can thus verify reasonably quickly whether the measured and calculated count rates are consistent.
TAGZIRIA Hamid;
PEERANI Paolo;
SCHWALBACH Peter;
KOEHNE Wilhelm;
2005-12-12
European Safeguards Research and Development Association (ESARDA)
JRC30785
https://publications.jrc.ec.europa.eu/repository/handle/JRC30785,
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