Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

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Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons. / Preston, Markus; Borella, Alessandro; Branger, Erik; Grape, Sophie; Rossa, Riccardo.

Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting: August 23-26 & August 30-September 1, 2021. INMM - Institute of Nuclear Materials Management , 2021. p. 1-10.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

Harvard

Preston, M, Borella, A, Branger, E, Grape, S & Rossa, R 2021, Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons. in Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting: August 23-26 & August 30-September 1, 2021. INMM - Institute of Nuclear Materials Management , pp. 1-10, 2021 - INMM/ESARDA Joint Annual Meeting , Austria, 2021-08-23. <https://resources.inmm.org/annual-meeting-proceedings/discriminating-between-irradiated-myrrha-fuel-and-light-water-reactor>

APA

Preston, M., Borella, A., Branger, E., Grape, S., & Rossa, R. (2021). Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons. In Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting: August 23-26 & August 30-September 1, 2021 (pp. 1-10). INMM - Institute of Nuclear Materials Management . https://resources.inmm.org/annual-meeting-proceedings/discriminating-between-irradiated-myrrha-fuel-and-light-water-reactor

Vancouver

Preston M, Borella A, Branger E, Grape S, Rossa R. Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons. In Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting: August 23-26 & August 30-September 1, 2021. INMM - Institute of Nuclear Materials Management . 2021. p. 1-10

Author

Preston, Markus ; Borella, Alessandro ; Branger, Erik ; Grape, Sophie ; Rossa, Riccardo. / Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons. Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting: August 23-26 & August 30-September 1, 2021. INMM - Institute of Nuclear Materials Management , 2021. pp. 1-10

Bibtex - Download

@inproceedings{9cb78357cb0a4a6a82d562de8d2fb1aa,
title = "Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons",
abstract = "MYRRHA is an accelerator-driven system featuring a MOX-fuelled core cooled by lead-bismuth eutectic, which is under development at SCK CEN in Mol, Belgium. An initial plutonium content of 30% in the fuel is foreseen, which together with the fast neutron spectrum in the core results in considerably different spent-fuel properties compared to spent fuel from typical light water reactors. These differences have been studied through depletion simulations, and include how radionuclide densities depend on burnup, which radionuclides contribute to the gamma-ray and neutron emission, and the intensity of the emitted radiation. As a consequence, current techniques for safeguards verification of spent fuel via non-destructive assay may need to be updated, or new techniques developed, for use in safeguarding of spent MYRRHA fuel. To some extent, these differences may have consequences in the wider context of nuclear safeguards for Generation IV systems. The focus of this paper is to what extent the gamma-ray and neutron signatures could be used to differentiate irradiated MYRRHA fuel from irradiated MOX and UO2 fuels from a light water reactor. The ability to discriminate between light-water-reactor MOX and UO2 has been recognised as an important task in safeguards verification today, and this work extends this objective to a future nuclear energy system.",
keywords = "Spent nuclear fuel, MYRRHA, Non-destructive assay (NDA), Classification",
author = "Markus Preston and Alessandro Borella and Erik Branger and Sophie Grape and Riccardo Rossa",
note = "Score=3; 2021 - INMM/ESARDA Joint Annual Meeting ; Conference date: 23-08-2021 Through 01-09-2021",
year = "2021",
month = sep,
day = "1",
language = "English",
pages = "1--10",
booktitle = "Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting",
publisher = "INMM - Institute of Nuclear Materials Management ",
url = "https://inmm.org/events/EventDetails.aspx?id=1518671",

}

RIS - Download

TY - GEN

T1 - Discriminating between irradiated MYRRHA fuel and light water reactor fuels using gamma rays and neutrons

AU - Preston, Markus

AU - Borella, Alessandro

AU - Branger, Erik

AU - Grape, Sophie

AU - Rossa, Riccardo

N1 - Score=3

PY - 2021/9/1

Y1 - 2021/9/1

N2 - MYRRHA is an accelerator-driven system featuring a MOX-fuelled core cooled by lead-bismuth eutectic, which is under development at SCK CEN in Mol, Belgium. An initial plutonium content of 30% in the fuel is foreseen, which together with the fast neutron spectrum in the core results in considerably different spent-fuel properties compared to spent fuel from typical light water reactors. These differences have been studied through depletion simulations, and include how radionuclide densities depend on burnup, which radionuclides contribute to the gamma-ray and neutron emission, and the intensity of the emitted radiation. As a consequence, current techniques for safeguards verification of spent fuel via non-destructive assay may need to be updated, or new techniques developed, for use in safeguarding of spent MYRRHA fuel. To some extent, these differences may have consequences in the wider context of nuclear safeguards for Generation IV systems. The focus of this paper is to what extent the gamma-ray and neutron signatures could be used to differentiate irradiated MYRRHA fuel from irradiated MOX and UO2 fuels from a light water reactor. The ability to discriminate between light-water-reactor MOX and UO2 has been recognised as an important task in safeguards verification today, and this work extends this objective to a future nuclear energy system.

AB - MYRRHA is an accelerator-driven system featuring a MOX-fuelled core cooled by lead-bismuth eutectic, which is under development at SCK CEN in Mol, Belgium. An initial plutonium content of 30% in the fuel is foreseen, which together with the fast neutron spectrum in the core results in considerably different spent-fuel properties compared to spent fuel from typical light water reactors. These differences have been studied through depletion simulations, and include how radionuclide densities depend on burnup, which radionuclides contribute to the gamma-ray and neutron emission, and the intensity of the emitted radiation. As a consequence, current techniques for safeguards verification of spent fuel via non-destructive assay may need to be updated, or new techniques developed, for use in safeguarding of spent MYRRHA fuel. To some extent, these differences may have consequences in the wider context of nuclear safeguards for Generation IV systems. The focus of this paper is to what extent the gamma-ray and neutron signatures could be used to differentiate irradiated MYRRHA fuel from irradiated MOX and UO2 fuels from a light water reactor. The ability to discriminate between light-water-reactor MOX and UO2 has been recognised as an important task in safeguards verification today, and this work extends this objective to a future nuclear energy system.

KW - Spent nuclear fuel

KW - MYRRHA

KW - Non-destructive assay (NDA)

KW - Classification

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/46290224

M3 - In-proceedings paper

SP - 1

EP - 10

BT - Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting

PB - INMM - Institute of Nuclear Materials Management

T2 - 2021 - INMM/ESARDA Joint Annual Meeting

Y2 - 23 August 2021 through 1 September 2021

ER -

ID: 7227144