Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time
Licenses for the storage of spent nuclear fuel (SNF) and vitrified highly active waste in casks under dry conditions are limited to 40 years and have to be renewed for prolonged storage periods. If such a license renewal has to be expected since as in accordance with the new site selection procedure...
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| Format: | Article |
| Language: | English |
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Elsevier
2018-03-01
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| Series: | Nuclear Engineering and Technology |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573317307453 |
| _version_ | 1811273749708668928 |
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| author | Gerold Spykman |
| author_facet | Gerold Spykman |
| author_sort | Gerold Spykman |
| collection | DOAJ |
| description | Licenses for the storage of spent nuclear fuel (SNF) and vitrified highly active waste in casks under dry conditions are limited to 40 years and have to be renewed for prolonged storage periods. If such a license renewal has to be expected since as in accordance with the new site selection procedure a final repository for spent fuel in Germany will not be available before the year 2050. For transport and possible unloading and loading in new casks for final storage, the integrity and the maintenance of the geometry of the cask's inventory is essential because the SNF rod cladding and the cladding of the vitrified highly active waste are stipulated as a barrier in the storage concept. For SNF, the cladding integrity is ensured currently by limiting the hoop stress and hoop strain as well as the maximum temperature to certain values for a 40-year storage period. For a prolonged storage period, other cladding degradation mechanisms such as inner and outer oxide layer formation, hydrogen pick up, irradiation damages in cladding material crystal structure, helium production from alpha decay, and long-term fission gas release may become leading effects driving degradation mechanisms that have to be discussed. Keywords: Barrier Concept, Cladding Integrity, Highly Active Waste, Prolonged Dry Storage, Spent Nuclear Fuel, Technical Support Organization |
| first_indexed | 2024-04-12T23:06:07Z |
| format | Article |
| id | doaj.art-c3d07bc59693426a9f9cdfb80b6f4516 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-04-12T23:06:07Z |
| publishDate | 2018-03-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-c3d07bc59693426a9f9cdfb80b6f45162022-12-22T03:12:55ZengElsevierNuclear Engineering and Technology1738-57332018-03-01502313317Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage timeGerold Spykman0TÜV NORD EnSys GmbH & Co. KG, Department Reactor Technology and Radiation Protection, Section Reactor Core Components, Am TÜV 1, 30519 Hanover, GermanyLicenses for the storage of spent nuclear fuel (SNF) and vitrified highly active waste in casks under dry conditions are limited to 40 years and have to be renewed for prolonged storage periods. If such a license renewal has to be expected since as in accordance with the new site selection procedure a final repository for spent fuel in Germany will not be available before the year 2050. For transport and possible unloading and loading in new casks for final storage, the integrity and the maintenance of the geometry of the cask's inventory is essential because the SNF rod cladding and the cladding of the vitrified highly active waste are stipulated as a barrier in the storage concept. For SNF, the cladding integrity is ensured currently by limiting the hoop stress and hoop strain as well as the maximum temperature to certain values for a 40-year storage period. For a prolonged storage period, other cladding degradation mechanisms such as inner and outer oxide layer formation, hydrogen pick up, irradiation damages in cladding material crystal structure, helium production from alpha decay, and long-term fission gas release may become leading effects driving degradation mechanisms that have to be discussed. Keywords: Barrier Concept, Cladding Integrity, Highly Active Waste, Prolonged Dry Storage, Spent Nuclear Fuel, Technical Support Organizationhttp://www.sciencedirect.com/science/article/pii/S1738573317307453 |
| spellingShingle | Gerold Spykman Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time Nuclear Engineering and Technology |
| title | Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time |
| title_full | Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time |
| title_fullStr | Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time |
| title_full_unstemmed | Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time |
| title_short | Dry storage of spent nuclear fuel and high active waste in Germany—Current situation and technical aspects on inventories integrity for a prolonged storage time |
| title_sort | dry storage of spent nuclear fuel and high active waste in germany current situation and technical aspects on inventories integrity for a prolonged storage time |
| url | http://www.sciencedirect.com/science/article/pii/S1738573317307453 |
| work_keys_str_mv | AT geroldspykman drystorageofspentnuclearfuelandhighactivewasteingermanycurrentsituationandtechnicalaspectsoninventoriesintegrityforaprolongedstoragetime |