Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield

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Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield. / Herranz, Margarita; Boden, Sven; Völgyesi, Péter; Idoeta, Raquel; Broeckx, Wouter; Ruiz González, Jesus; Otiougova, Polina; Klix, Axel; Leong, Lou Sai; Hlavathy, Zoltán; Almási, István; Amgarou, Khalil; Crozet, Marielle; Legarda, Fernando.

In: Progress in Nuclear Energy, Vol. 137, 103740, 01.07.2021, p. 1-13.

Research output: Contribution to journalArticlepeer-review

Harvard

Herranz, M, Boden, S, Völgyesi, P, Idoeta, R, Broeckx, W, Ruiz González, J, Otiougova, P, Klix, A, Leong, LS, Hlavathy, Z, Almási, I, Amgarou, K, Crozet, M & Legarda, F 2021, 'Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield', Progress in Nuclear Energy, vol. 137, 103740, pp. 1-13. https://doi.org/10.1016/j.pnucene.2021.103740

APA

Herranz, M., Boden, S., Völgyesi, P., Idoeta, R., Broeckx, W., Ruiz González, J., Otiougova, P., Klix, A., Leong, L. S., Hlavathy, Z., Almási, I., Amgarou, K., Crozet, M., & Legarda, F. (2021). Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield. Progress in Nuclear Energy, 137, 1-13. [103740]. https://doi.org/10.1016/j.pnucene.2021.103740

Vancouver

Author

Herranz, Margarita ; Boden, Sven ; Völgyesi, Péter ; Idoeta, Raquel ; Broeckx, Wouter ; Ruiz González, Jesus ; Otiougova, Polina ; Klix, Axel ; Leong, Lou Sai ; Hlavathy, Zoltán ; Almási, István ; Amgarou, Khalil ; Crozet, Marielle ; Legarda, Fernando. / Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield. In: Progress in Nuclear Energy. 2021 ; Vol. 137. pp. 1-13.

Bibtex - Download

@article{d6a0d951ab8d43a68b830bf6abe68198,
title = "Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield",
abstract = "Nearly all decommissioning and dismantling (D&D) projects are steered by the characterisation of the plant being dismantled. This radiological characterisation is a complex process that is updated and modified during the course of the D&D. One of the tools for carrying out this characterisation is the performance of in-situ measurements. There is a wide variety of equipment and methodologies used to carry out on-site measurements, depending on the environment in which they are to be carried out and also on the specific objectives of the measurements and the financial and personnel resources available. The extent to which measurements carried out with different types of equipment or methodologies providing comparable results can be crucial in view of the D&D strategy development and the decision-making process. This paper concerns an on-site benchmarking exercise carried out at the activated biological shield of Belgian Reactor 3 (BR3). This activity allows comparison and validation of characterisation methodologies and different equipment used as well as future interpretation of final results in terms of uncertainties and sensitivities. This paper describes the measurements and results from the analysis of this exercise. Other aspects of this exercise will be reported in separate papers. This paper provides an overview of the on-site benchmarking exercise, outlines the participating organisations and the measurement equipment used for total gamma, dose rate and gamma spectrometry measurements and finally, results obtained and their interpretations are discussed for each type of measurement as a function of detector type. Regarding the dose measurements, results obtained by using a large variety of equipment are very consistent. In view of mapping the inner surface of the biological shield the most appropriate equipment tested might be the organic scintillator, the BGO or even the ionisation chamber. In addition, for mapping this surface, the most appropriate total gamma equipment tested might be the LaBr3(Ce), the thick organic scintillator or the BGO. These measurements can only be used as a secondary parameter in a relative way. Results for the gamma spectrometry are very consistent for all the equipment used and the main parameters to be determined.",
keywords = "Radiological characterisation, D&D processes, Dose-rate measurements, Total gamma measurements, In-situ gamma-ray spectrometry",
author = "Margarita Herranz and Sven Boden and P{\'e}ter V{\"o}lgyesi and Raquel Idoeta and Wouter Broeckx and {Ruiz Gonz{\'a}lez}, Jesus and Polina Otiougova and Axel Klix and Leong, {Lou Sai} and Zolt{\'a}n Hlavathy and Istv{\'a}n Alm{\'a}si and Khalil Amgarou and Marielle Crozet and Fernando Legarda",
note = "Score=10",
year = "2021",
month = jul,
day = "1",
doi = "10.1016/j.pnucene.2021.103740",
language = "English",
volume = "137",
pages = "1--13",
journal = "Progress in Nuclear Energy",
issn = "0149-1970",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield

AU - Herranz, Margarita

AU - Boden, Sven

AU - Völgyesi, Péter

AU - Idoeta, Raquel

AU - Broeckx, Wouter

AU - Ruiz González, Jesus

AU - Otiougova, Polina

AU - Klix, Axel

AU - Leong, Lou Sai

AU - Hlavathy, Zoltán

AU - Almási, István

AU - Amgarou, Khalil

AU - Crozet, Marielle

AU - Legarda, Fernando

N1 - Score=10

PY - 2021/7/1

Y1 - 2021/7/1

N2 - Nearly all decommissioning and dismantling (D&D) projects are steered by the characterisation of the plant being dismantled. This radiological characterisation is a complex process that is updated and modified during the course of the D&D. One of the tools for carrying out this characterisation is the performance of in-situ measurements. There is a wide variety of equipment and methodologies used to carry out on-site measurements, depending on the environment in which they are to be carried out and also on the specific objectives of the measurements and the financial and personnel resources available. The extent to which measurements carried out with different types of equipment or methodologies providing comparable results can be crucial in view of the D&D strategy development and the decision-making process. This paper concerns an on-site benchmarking exercise carried out at the activated biological shield of Belgian Reactor 3 (BR3). This activity allows comparison and validation of characterisation methodologies and different equipment used as well as future interpretation of final results in terms of uncertainties and sensitivities. This paper describes the measurements and results from the analysis of this exercise. Other aspects of this exercise will be reported in separate papers. This paper provides an overview of the on-site benchmarking exercise, outlines the participating organisations and the measurement equipment used for total gamma, dose rate and gamma spectrometry measurements and finally, results obtained and their interpretations are discussed for each type of measurement as a function of detector type. Regarding the dose measurements, results obtained by using a large variety of equipment are very consistent. In view of mapping the inner surface of the biological shield the most appropriate equipment tested might be the organic scintillator, the BGO or even the ionisation chamber. In addition, for mapping this surface, the most appropriate total gamma equipment tested might be the LaBr3(Ce), the thick organic scintillator or the BGO. These measurements can only be used as a secondary parameter in a relative way. Results for the gamma spectrometry are very consistent for all the equipment used and the main parameters to be determined.

AB - Nearly all decommissioning and dismantling (D&D) projects are steered by the characterisation of the plant being dismantled. This radiological characterisation is a complex process that is updated and modified during the course of the D&D. One of the tools for carrying out this characterisation is the performance of in-situ measurements. There is a wide variety of equipment and methodologies used to carry out on-site measurements, depending on the environment in which they are to be carried out and also on the specific objectives of the measurements and the financial and personnel resources available. The extent to which measurements carried out with different types of equipment or methodologies providing comparable results can be crucial in view of the D&D strategy development and the decision-making process. This paper concerns an on-site benchmarking exercise carried out at the activated biological shield of Belgian Reactor 3 (BR3). This activity allows comparison and validation of characterisation methodologies and different equipment used as well as future interpretation of final results in terms of uncertainties and sensitivities. This paper describes the measurements and results from the analysis of this exercise. Other aspects of this exercise will be reported in separate papers. This paper provides an overview of the on-site benchmarking exercise, outlines the participating organisations and the measurement equipment used for total gamma, dose rate and gamma spectrometry measurements and finally, results obtained and their interpretations are discussed for each type of measurement as a function of detector type. Regarding the dose measurements, results obtained by using a large variety of equipment are very consistent. In view of mapping the inner surface of the biological shield the most appropriate equipment tested might be the organic scintillator, the BGO or even the ionisation chamber. In addition, for mapping this surface, the most appropriate total gamma equipment tested might be the LaBr3(Ce), the thick organic scintillator or the BGO. These measurements can only be used as a secondary parameter in a relative way. Results for the gamma spectrometry are very consistent for all the equipment used and the main parameters to be determined.

KW - Radiological characterisation

KW - D&D processes

KW - Dose-rate measurements

KW - Total gamma measurements

KW - In-situ gamma-ray spectrometry

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/43826803

U2 - 10.1016/j.pnucene.2021.103740

DO - 10.1016/j.pnucene.2021.103740

M3 - Article

VL - 137

SP - 1

EP - 13

JO - Progress in Nuclear Energy

JF - Progress in Nuclear Energy

SN - 0149-1970

M1 - 103740

ER -

ID: 7123361