Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels

Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with spent nuclear fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specif...

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Main Authors: Mahdi Rezaeian, Jamshid Kamali
Format: Article
Language:English
Published: Wiley 2016-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2016/4579738
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author Mahdi Rezaeian
Jamshid Kamali
author_facet Mahdi Rezaeian
Jamshid Kamali
author_sort Mahdi Rezaeian
collection DOAJ
description Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with spent nuclear fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the spent fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for spent fuel management of Bushehr nuclear power plant.
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spelling doaj-art-5aec49d0cfb442458d77ee399e1e6cca2025-08-20T03:35:00ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832016-01-01201610.1155/2016/45797384579738Radioactive Source Specification of Bushehr’s VVER-1000 Spent FuelsMahdi Rezaeian0Jamshid Kamali1Nuclear Science and Technology Research Institute, Tehran 11365-8486, IranAmirkabir University of Technology, Tehran 15875-4413, IranDue to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with spent nuclear fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the spent fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for spent fuel management of Bushehr nuclear power plant.http://dx.doi.org/10.1155/2016/4579738
spellingShingle Mahdi Rezaeian
Jamshid Kamali
Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels
Science and Technology of Nuclear Installations
title Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels
title_full Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels
title_fullStr Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels
title_full_unstemmed Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels
title_short Radioactive Source Specification of Bushehr’s VVER-1000 Spent Fuels
title_sort radioactive source specification of bushehr s vver 1000 spent fuels
url http://dx.doi.org/10.1155/2016/4579738
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