Czech national programme and disposal canister concept
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F17%3AN0000020" target="_blank" >RIV/46356088:_____/17:N0000020 - isvavai.cz</a>
Alternative codes found
RIV/60461373:22310/17:43914252
Result on the web
<a href="http://dx.doi.org/10.1080/1478422X.2017.1300379" target="_blank" >http://dx.doi.org/10.1080/1478422X.2017.1300379</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1080/1478422X.2017.1300379" target="_blank" >10.1080/1478422X.2017.1300379</a>
Alternative languages
Result language
angličtina
Original language name
Czech national programme and disposal canister concept
Original language description
The Czech Republic has a well-developed nuclear programme with two nuclear power plants currently in operation and three operational near-surface repositories serving for the disposal of institutional and operational low- and intermediate-level waste. Spent nuclear fuel will be disposed of in a deep geological repository to be constructed in crystalline or metamorphic rock approximately 500 m below the surface. Czech Ca–Mg bentonites will be used as the buffer and backfilling material. Steel-based materials are currently considered as the reference metallic materials in the Czech disposal canister concept. The preferred design is based on a double-walled canister with an inner shell of stainless steel and an outer shell of carbon-steel. Both parts of the canister must provide mechanical stability; the wall of the carbon-steel canister will be strengthened for corrosion-resistance purposes. The presented work focuses on canister design as confirmed by means of mechanical, thermal and criticality calculations and a detailed experimental corrosion plan. This paper is part of a supplement on the 6th International Workshop on Long-Term Prediction of Corrosion Damage in Nuclear Waste Systems.
Czech name
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Czech description
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Classification
Type
J<sub>SC</sub> - Article in a specialist periodical, which is included in the SCOPUS database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
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Continuities
V - Vyzkumna aktivita podporovana z jinych verejnych zdroju
Others
Publication year
2017
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Corrosion Engineering Science and Technology
ISSN
1478-422X
e-ISSN
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Volume of the periodical
52
Issue of the periodical within the volume
April
Country of publishing house
GB - UNITED KINGDOM
Number of pages
5
Pages from-to
6-10
UT code for WoS article
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EID of the result in the Scopus database
2-s2.0-85028774910