An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

Peter Schillebeeckx, Marc Verwerft, Pablo Romojaro, Gasper Zerovnik, Nadia Messaoudi, Gery Alaerts, Luca Fiorito, Kevin Govers, Jan Paepen, Yves Parthoens, Bent Pedersen, Alexey Stankovskiy, Gert Van den Eynde, Ruud Wynants

Research outputpeer-review


A method to determine the neutron production rate of a spent nuclear fuel segment sample by means of non-destructive assay conducted under standard controlled-area conditions is described and demonstrated. A 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 SCK CEN in Belgium. Experiments with 252Cf(sf) sources, certified for their neutron emission rate, were carried out at the Joint Research Centre to determine the characteristics of the detection device. Measurements of a segment of a spent nuclear fuel rod were carried out at SCK CEN resulting in an absolute and non-destructive measurement of the neutron production rate avoiding any reference to a representative spent nuclear fuel sample to calibrate the device. Results of these measurements were used to study the performance of depletion codes, i.e., ALEPH2, SCALE, and Serpent2. The study includes a code-to-code and code-to-experiment comparison using different nuclear data libraries.
Original languageEnglish
Article number1162367
Number of pages15
JournalFrontiers in Energy Research
StatePublished - 24 Apr 2023

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Economics and Econometrics
  • Fuel Technology
  • Renewable Energy, Sustainability and the Environment

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