Czech national programme and disposal canister concept

Kód výsledku v 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>

Nalezeny alternativní kódy

RIV/60461373:22310/17:43914252

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

Czech national programme and disposal canister concept

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Czech national programme and disposal canister concept

Popis výsledku anglicky

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.

Druh

J_SC - Článek v periodiku v databázi SCOPUS

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

—

Návaznosti

V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Rok uplatnění

2017

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Corrosion Engineering Science and Technology

ISSN

1478-422X

e-ISSN

—

Svazek periodika

52

Číslo periodika v rámci svazku

April

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

5

Strana od-do

6-10

Kód UT WoS článku

—

EID výsledku v databázi Scopus

2-s2.0-85028774910