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

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 me...

Full description

Bibliographic Details
Main Authors: Peter Schillebeeckx, M. Verwerft, P. Romojaro, G. Žerovnik, N. Messaoudi, G. Alaerts, L. Fiorito, K. Govers, J. Paepen, Y. Parthoens, B. Pedersen, A. Stankovskiy, G. Van den Eynde, R. Wynants
Format: Article
Language:English
Published: Frontiers Media S.A. 2023-04-01
Series:Frontiers in Energy Research
Subjects:
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2023.1162367/full
_version_ 1797835097205899264
author Peter Schillebeeckx
M. Verwerft
P. Romojaro
G. Žerovnik
N. Messaoudi
G. Alaerts
L. Fiorito
K. Govers
J. Paepen
Y. Parthoens
B. Pedersen
A. Stankovskiy
G. Van den Eynde
R. Wynants
author_facet Peter Schillebeeckx
M. Verwerft
P. Romojaro
G. Žerovnik
N. Messaoudi
G. Alaerts
L. Fiorito
K. Govers
J. Paepen
Y. Parthoens
B. Pedersen
A. Stankovskiy
G. Van den Eynde
R. Wynants
author_sort Peter Schillebeeckx
collection DOAJ
description 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.
first_indexed 2024-04-09T14:48:50Z
format Article
id doaj.art-6baf1f31a2914f99b0af33c144dffa92
institution Directory Open Access Journal
issn 2296-598X
language English
last_indexed 2024-04-09T14:48:50Z
publishDate 2023-04-01
publisher Frontiers Media S.A.
record_format Article
series Frontiers in Energy Research
spelling doaj.art-6baf1f31a2914f99b0af33c144dffa922023-05-02T10:21:07ZengFrontiers Media S.A.Frontiers in Energy Research2296-598X2023-04-011110.3389/fenrg.2023.11623671162367An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validationPeter Schillebeeckx0M. Verwerft1P. Romojaro2G. Žerovnik3N. Messaoudi4G. Alaerts5L. Fiorito6K. Govers7J. Paepen8Y. Parthoens9B. Pedersen10A. Stankovskiy11G. Van den Eynde12R. Wynants13European Commission, Joint Research Centre (JRC), Geel, BelgiumBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumJožef Stefan Institute (JSI), Ljubljana, SloveniaBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumEuropean Commission, Joint Research Centre (JRC), Geel, BelgiumBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumEuropean Commission, Joint Research Centre (JRC), Geel, BelgiumBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumEuropean Commission, Joint Research Centre (JRC), Ispra, ItalyBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumBelgian Nuclear Research Centre (SCK CEN), Mol, BelgiumEuropean Commission, Joint Research Centre (JRC), Geel, BelgiumA 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.https://www.frontiersin.org/articles/10.3389/fenrg.2023.1162367/fullneutron emissionneutron correlation countingspent nuclear fuel (SNF)depletion calculationspontaneous fission
spellingShingle Peter Schillebeeckx
M. Verwerft
P. Romojaro
G. Žerovnik
N. Messaoudi
G. Alaerts
L. Fiorito
K. Govers
J. Paepen
Y. Parthoens
B. Pedersen
A. Stankovskiy
G. Van den Eynde
R. Wynants
An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
Frontiers in Energy Research
neutron emission
neutron correlation counting
spent nuclear fuel (SNF)
depletion calculation
spontaneous fission
title An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
title_full An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
title_fullStr An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
title_full_unstemmed An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
title_short An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
title_sort absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
topic neutron emission
neutron correlation counting
spent nuclear fuel (SNF)
depletion calculation
spontaneous fission
url https://www.frontiersin.org/articles/10.3389/fenrg.2023.1162367/full
work_keys_str_mv AT peterschillebeeckx anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT mverwerft anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT promojaro anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT gzerovnik anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT nmessaoudi anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT galaerts anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT lfiorito anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT kgovers anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT jpaepen anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT yparthoens anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT bpedersen anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT astankovskiy anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT gvandeneynde anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT rwynants anabsolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT peterschillebeeckx absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT mverwerft absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT promojaro absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT gzerovnik absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT nmessaoudi absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT galaerts absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT lfiorito absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT kgovers absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT jpaepen absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT yparthoens absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT bpedersen absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT astankovskiy absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT gvandeneynde absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation
AT rwynants absolutemeasurementoftheneutronproductionrateofaspentnuclearfuelsampleusedfordepletioncodevalidation