Dose characteristics in fuel containing material
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F13%3A%230000797" target="_blank" >RIV/26722445:_____/13:#0000797 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Dose characteristics in fuel containing material
Original language description
Poster at the 1st International Conference on Dosimetry and its Applications, Prague, Czech Republic, 23-28 June 2013. Spent fuel containing material, also called corium, arises during a severe nuclear reactor accident through the melting of the reactorcore and surrounding material. It consists of nuclear fuel, fission products, activation products, control rods and other structural material. After a reactor accident, corium remains in a molten phase for some time, mainly due to fission products decayheating. When this heating decreases and/or cooling is applied, the corium changes to a solid state. This paper deals with dose characteristics inside the spent fuel containing material after transition of the molten mixture to a solid state. For calculations, simplified models of fuel containing material were used.
Czech name
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Czech description
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Classification
Type
O - Miscellaneous
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
<a href="/en/project/LH12224" target="_blank" >LH12224: Modelling and investigation of non-standard situations of new type of nuclear reactors</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2013
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů