A method to determine the neutron production rate of a sample of spent nuclear fuel by means of non-destructive analysis conducted under controlled-area conditions is described, validated and demonstrated. A standard neutron well-counter designed for routine nuclear safeguards applications is applied. The method relies on a transfer procedure that is adapted to the hot-cell facilities at the laboratory for high and medium level activity of the SCK CEN. The sample transfer and measurement procedures are described together with results of Monte Carlo simulations. Experiments with radionuclide sources were carried out at the Joint Research Centre to test the procedures and to determine the performance characteristics of the detection device. Finally, measurements of a segment of a spent nuclear fuel rod were carried out at the SCK CEN to validate and demonstrate the method.
SCHILLEBEECKX Peter;
VERWERFT M.;
ZEROVNIK Gasper;
PARTHOENS Y.;
PEDERSEN Bent;
ALAERTS Gery;
COOLS Gerry;
GOVERS Kevin;
PAEPEN Jan;
VARASANO Giovanni;
WYNANTS Ruud;
2020-09-30
Publications Office of the European Union
JRC121586
978-92-76-22349-8 (online),
1831-9424 (online),
EUR 30379 EN,
OP KJ-NA-30379-EN-N (online),
https://publications.jrc.ec.europa.eu/repository/handle/JRC121586,
10.2760/614853 (online),
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