Research output: Report/book › ER - External report › peer-review
A non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditions. / Schillebeeckx, Peter; Verwerft, Marc; Zerovnik, Gasper; Parthoens, Yves; Pedersen, Bent; Alaerts, Gery; Cools, Gerry; Govers, Kevin; Paepen, Jan; Varasano, Giovanni; Wynants, Ruud.
European Atomic Energy Community, 2020. 54 p. (Publications Office of the European Union; No. EUR 30379 EN).Research output: Report/book › ER - External report › peer-review
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TY - BOOK
T1 - A non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditions
AU - Schillebeeckx, Peter
AU - Verwerft, Marc
AU - Zerovnik, Gasper
AU - Parthoens, Yves
AU - Pedersen, Bent
AU - Alaerts, Gery
AU - Cools, Gerry
AU - Govers, Kevin
AU - Paepen, Jan
AU - Varasano, Giovanni
AU - Wynants, Ruud
N1 - Score=1
PY - 2020/9/30
Y1 - 2020/9/30
N2 - 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.
AB - 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.
KW - Spent nuclear fuel
KW - EURAD
KW - REGAL
KW - Neutron emission
UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/45823034
U2 - 10.2760/614853
DO - 10.2760/614853
M3 - ER - External report
SN - 978-92-76-22349-8
T3 - Publications Office of the European Union
BT - A non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditions
PB - European Atomic Energy Community
ER -
ID: 7203437