Dose characteristics in fuel containing material

Kód výsledku v 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>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Dose characteristics in fuel containing material

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Dose characteristics in fuel containing material

Popis výsledku anglicky

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.

Druh

O - Ostatní výsledky

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/LH12224" target="_blank" >LH12224: Modelování a výzkum hypotetických nestandardních situací jaderných reaktorů nového typu</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2013

Kód důvěrnosti údajů

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