A non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditions

Research output: Report/bookER - External reportpeer-review

Authors

Institutes & Expert groups

  • JRC - Joint Research Centre
  • EC - JRC - European Commission - Joint Research Centre

Documents & links

DOI

Abstract

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.

Details

Original languageEnglish
PublisherEuropean Atomic Energy Community
Number of pages54
ISBN (Print)978-92-76-22349-8
DOIs
Publication statusPublished - 30 Sep 2020

Publication series

NamePublications Office of the European Union
PublisherEuropean Atomic Energy Community
No.EUR 30379 EN
ISSN (Print)1831-9424

Keywords

  • Spent nuclear fuel, EURAD, REGAL, Neutron emission

ID: 7203437