The revised German Atomic Act together with the Agreement between the German Government and the German Utilities of June 11, 2001 form new boundary conditions that considerably influence spent fuel strategies by stipulation of lifetime limitations to nuclear power plants and termination of reprocessing. The contractually agreed return of reprocessing residues comprises some 156 casks containing vitrified highly active waste, the so-called HAW or glass canisters, coming form irradiated nuclear fuel assemblies to be shipped from COGEMA, France and BNFL, UK to Germany presumably until 2011. Several hundred casks with compacted residues and other waste will follow. The transports are scheduled presumably beyond 2020. The central interim storage facilities in Ahaus and Gorleben, formerly intended to accumulate up to 8,000 t of heavy metal (HM) of spent fuel from German nuclear power plants, offer sufficient capacity to receive the totality of residues to be returned from reprocessing abroad. GNB has developed, tested, licensed, fabricated, loaded, transported and stored a large number of casks for spent fuel and is one of the world leaders for delivering spent fuel and high level waste casks. Long-term intermediate storage of spent fuel is carried out under dry conditions using these casks that are licensed for transport as well as for storage. Standardized high performance casks such as the types CASTOR® HAW 20/28 CG, CASTOR® V/19 and CASTOR® V/52 meet the needs of most nuclear power plants in Germany. Up to now GNS has co-ordinated the loading and transport of 27 casks loaded with 28 canisters each from COGEMA back to Germany for storage in Gorleben for up to 40 years. In all but one case the cask type CASTOR® HAW 20/28 CG has been used.
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ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
September 21–25, 2003
Oxford, England
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
0-7918-3732-7
PROCEEDINGS PAPER
Design, Loading, Transport and Storage Experience of CASTOR® Casks for Vitrified High Level Waste
Andre´ Voßnacke,
Andre´ Voßnacke
GNB Gesellschaft fu¨r Nuklear-Beha¨lter mbH
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Wilhelm Graf,
Wilhelm Graf
GNS Gesellschaft fu¨r Nuklear-Service mbH
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Roland Hu¨ggenberg,
Roland Hu¨ggenberg
GNB Gesellschaft fu¨r Nuklear-Beha¨lter mbH
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Astrid Gisbertz
Astrid Gisbertz
GNS Gesellschaft fu¨r Nuklear-Service mbH
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Andre´ Voßnacke
GNB Gesellschaft fu¨r Nuklear-Beha¨lter mbH
Wilhelm Graf
GNS Gesellschaft fu¨r Nuklear-Service mbH
Roland Hu¨ggenberg
GNB Gesellschaft fu¨r Nuklear-Beha¨lter mbH
Astrid Gisbertz
GNS Gesellschaft fu¨r Nuklear-Service mbH
Paper No:
ICEM2003-4724, pp. 1215-1219; 5 pages
Published Online:
February 24, 2009
Citation
Voßnacke, A, Graf, W, Hu¨ggenberg, R, & Gisbertz, A. "Design, Loading, Transport and Storage Experience of CASTOR® Casks for Vitrified High Level Waste." Proceedings of the ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3. Oxford, England. September 21–25, 2003. pp. 1215-1219. ASME. https://doi.org/10.1115/ICEM2003-4724
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