[논문]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

Spykman, Gerold

doi:10.1016/j.net.2018.01.009

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 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.50 no.2, 2018년, pp.313 - 317

Spykman, Gerold (TUV NORD EnSys GmbH & Co. KG, Department Reactor Technology and Radiation Protection, Section Reactor Core Components)

Abstract ▼ AI-Helper

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.

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제안 방법

As the driving force for the strain, the hoop stress of the individual fuel rods is used or the covering value of 120 N/mm² are used. The author uses the fuel rod performance code TRANSURANUS [10] and a conservative approach in data and model selection for the assessment of the in-pile performance of the fuel and its behavior during the dry storage period. In this way, he uses specifications and drawings to obtain appropriate input data for the fuel rod and the individual power histories obtained from the utility.
The fulfillment of these and other requirements has to be shown by the utility and is assessed by the authority and its TSO. The proof of the cladding hoop stress considers the irradiation history of the fuel, especially the fuel rod inner pressure and the accumulated outer oxide layer. The hoop strain criterion is calculated by material-specific correlations for the time span of 40 years.
Similar temperature measurements are performed on casks containing vitrified HAW. The purpose of these measurements is to check the maximum allowed temperature of the cask internal moderator instead of the inventory temperatures.

성능/효과

3. High burnup fuel and mixed oxide fuel are identified as fuels with the highest loads and with the highest potential for systematic cladding failure (see also IAEA Standard on Storage of Spent Nuclear Fuel [4]).

후속연구

In the first step, it will be investigated whether the fuel rod performance codes are able to predict the 40-year interim storage period with the requirements mentioned in chapter II. Furthermore, it will be investigated which data from manufacturing, in-pile life, and storage of the fuel are needed to predict the present requirements and what might be needed for future investigations when new models for new requirements are available. The latter is very important in Germany because it can be expected that after the nuclear phaseout in 2022 and the decommissioning of the nuclear power plants, there will be a potential risk of losing data and knowledge about the fuel that will be kept in interim storage.
These examinations should be used for the development of models to be used for the forecast of fuel performance during longer storage times. It is planned to implement new models in available fuel performance codes to perform full-fuel lifetime calculations, including the interim storage period, and also to take benefit from the methods of sensitivity analyses and probabilistic methods. Data and knowledge management aspects are identified as being as important as technical considerations.
The assessment of these effects may make some experimental examinations of spent fuel after a longer storage time necessary in future. These examinations should be used for the development of models to be used for the forecast of fuel performance during longer storage times. It is planned to implement new models in available fuel performance codes to perform full-fuel lifetime calculations, including the interim storage period, and also to take benefit from the methods of sensitivity analyses and probabilistic methods.

참고문헌 (13)

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Empfehlung der Entsorgungskommission, Leitlinien fur die trockene Zwischenlagerung bestrahlter Brennelemente und Warme entwickelnder radioaktiver Abfalle in Behaltern, Revidierte Fassung von (2013), 10.06.
International Atomic Energy Agency, Storage of Spent Nuclear Fuel, IAEA Safety Standard Series No. SSG-15, International Atomic Energy Agency, Vienna, 2012.
Verordnung uber den Schutz vor Schaden durch ionisierende Strahlen (Strahlenschutzverordnung - StrlSchV), Strahlenschutzverordnung vom 20. Juli 2001 (BGBl. I S. 1714; 2002 I S. 1459), die zuletzt durch nach MaBgabe des Artikel 10 durch Artikel 6 des Gesetzes vom 27. Januar 2017 (BGBl. I S. 114) geandert worden ist.
M. Peehs, F. Garzarolli, W. Goll, SIEMENS KWU-NBT, Erlangen, Germany, Assessment of dry storage performance of spent LWR fuel assemblies with increasing burnup, in: "Storage of Spent Fuel from Power Reactors", Vienna, 9-13 November 1998, IAEA-TECDOC-1089, SM-352/39, 1999, pp. 313-323 issued July.
W. Goll, H. Spilker, E. Toscano, Short-time creep and rupture tests on high burnup fuel rod cladding, J. Nucl. Mat. 289 (2001) 247-253.

상세보기
W. Goll, A.C. Leger, K. McCoy, in: Proceeding of Water Reactor Fuel Performance Meeting, Top Fuel 2003, March 16th-19th, 2003. Wurzburg, Germany.
H. Spilker, M. Peehs, H.-P. Dyck, G. Kaspar, K. Nissen, J. Nucl. Mat. 250 (1997) 63-74.

상세보기
P. Van Uffelen, Cs Gyori, A. Schubert, J. van de Laar, Z. Hozer, G. Spykman, Extending the application range of a fuel performance code from normal operating to design basis accident conditions, J. Nucl. Mat. 383 (2008) 137-143.

상세보기
G. Spykman, Cladding integrity during dry storage; verification for an exclusion of a systematic cladding failure during a forty year dry storage period and beyond, in: International Workshop on Safety of Long Term Interim Storage, Munich 21-23, May 2013.
G. Spykman, Specific aspects of high burnup or mixed oxide fuel rods during dry storage, in: IAEA International Conference on the Management of Spent Fuel from Nuclear Power Reactors, Vienna, 15.-19, June 2015, pp. 226-276. Paper IAEA-CN.
Extended Storage Collaboration Program, International Subcommittee Report, International Perspectives on Technical Data Gaps Associated with Extended Storage and Transportation of Used Fuel, EPRI, Palo Alto, CA, 2012, p. 1026481. Final Report, November 2012.

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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 원문보기

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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 원문보기

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