Evaluation of functional loss to radiation detector in tomographic device for spent-fuel inspection by high-energy photons and neutrons: A preliminary study

Hyojun Park; Hyung Joo Choi; Hyun Joon Choi; Yoon Soo Chung; Hyun Chul Lee; Chul Hee Min

doi:10.1016/j.anucene.2022.109558

Evaluation of functional loss to radiation detector in tomographic device for spent-fuel inspection by high-energy photons and neutrons: A preliminary study

Hyojun Park, Hyung Joo Choi, Hyun Joon Choi, Yoon Soo Chung, Hyun Chul Lee, Chul Hee Min

Radiological Science

Research output: Contribution to journal › Article › peer-review

Abstract

The aim of this study was to investigate functional loss of radiation detectors used for spent fuel inspections due to radiations from spent fuel. Dose to a radiation detector was evaluated by Geant4 simulation. Subsequently, the radiation detector measured counts, according to the irradiation time, for the test source with presence of external ⁶⁰Co and ²⁵²Cf sources in almost identical condition to those of the simulation, where gamma and neutron emission rates of the sources were similar to the actual spent fuels. The counts during the ⁶⁰Co irradiation were changed with discrepancy of 1.17% while neutron beam decreased more than 25% of total counts after its irradiation. Additionally, abnormalities in the detector's measured background counts were observed following the neutron irradiation. The results can be applied to efforts to define the tolerance dose for radiation detectors used in neutron-abundant environments such as nuclear power plants or spent-fuel storage facilities.

Original language	English
Article number	109558
Journal	Annals of Nuclear Energy
Volume	181
DOIs	https://doi.org/10.1016/j.anucene.2022.109558
Publication status	Published - 2023 Feb

Bibliographical note

Funding Information:
This research was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2101073), the Korea Institute of Energy Technology Evaluation and Planning (KETEP), and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. G032579811). The authors also thank the Korea Hydro & Nuclear Power Co. (KHNP) and Korean Association for Radiation Application’s research group.

Funding Information:
This research was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2101073), the Korea Institute of Energy Technology Evaluation and Planning (KETEP), and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. G032579811). The authors also thank the Korea Hydro & Nuclear Power Co. (KHNP) and Korean Association for Radiation Application's research group.

Publisher Copyright:
© 2022 Elsevier Ltd

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering

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10.1016/j.anucene.2022.109558

Cite this

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title = "Evaluation of functional loss to radiation detector in tomographic device for spent-fuel inspection by high-energy photons and neutrons: A preliminary study",

abstract = "The aim of this study was to investigate functional loss of radiation detectors used for spent fuel inspections due to radiations from spent fuel. Dose to a radiation detector was evaluated by Geant4 simulation. Subsequently, the radiation detector measured counts, according to the irradiation time, for the test source with presence of external 60Co and 252Cf sources in almost identical condition to those of the simulation, where gamma and neutron emission rates of the sources were similar to the actual spent fuels. The counts during the 60Co irradiation were changed with discrepancy of 1.17% while neutron beam decreased more than 25% of total counts after its irradiation. Additionally, abnormalities in the detector's measured background counts were observed following the neutron irradiation. The results can be applied to efforts to define the tolerance dose for radiation detectors used in neutron-abundant environments such as nuclear power plants or spent-fuel storage facilities.",

author = "Hyojun Park and Choi, {Hyung Joo} and Choi, {Hyun Joon} and Chung, {Yoon Soo} and Lee, {Hyun Chul} and Min, {Chul Hee}",

note = "Funding Information: This research was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2101073), the Korea Institute of Energy Technology Evaluation and Planning (KETEP), and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. G032579811). The authors also thank the Korea Hydro & Nuclear Power Co. (KHNP) and Korean Association for Radiation Application{\textquoteright}s research group. Funding Information: This research was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2101073), the Korea Institute of Energy Technology Evaluation and Planning (KETEP), and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. G032579811). The authors also thank the Korea Hydro & Nuclear Power Co. (KHNP) and Korean Association for Radiation Application's research group. Publisher Copyright: {\textcopyright} 2022 Elsevier Ltd",

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PY - 2023/2

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N2 - The aim of this study was to investigate functional loss of radiation detectors used for spent fuel inspections due to radiations from spent fuel. Dose to a radiation detector was evaluated by Geant4 simulation. Subsequently, the radiation detector measured counts, according to the irradiation time, for the test source with presence of external 60Co and 252Cf sources in almost identical condition to those of the simulation, where gamma and neutron emission rates of the sources were similar to the actual spent fuels. The counts during the 60Co irradiation were changed with discrepancy of 1.17% while neutron beam decreased more than 25% of total counts after its irradiation. Additionally, abnormalities in the detector's measured background counts were observed following the neutron irradiation. The results can be applied to efforts to define the tolerance dose for radiation detectors used in neutron-abundant environments such as nuclear power plants or spent-fuel storage facilities.

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Evaluation of functional loss to radiation detector in tomographic device for spent-fuel inspection by high-energy photons and neutrons: A preliminary study

Abstract

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