Research of dosimetric characteristics of fuel containing material

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001076" target="_blank" >RIV/26722445:_____/15:#0001076 - 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

Research of dosimetric characteristics of fuel containing material

Popis výsledku v původním jazyce

In case of serious nuclear reactor accident the molten fuel can melt through the reactor containment and radioactive material can escape into the environment. A core-catcher filled with a sacrificial material is suggested under the reactor vessel to prevent such release of radioactivity. The sacrificial material should fix up thermal and chemical stabilization of the melt and prevent the creation of undesirable aerosols during the following years. This paper estimates the absorbed dose in hypothetical material for different types of radiation. The main part of the dose comes from alpha, beta and gamma radiation. Based on the estimates and calculations the irradiation experiments were designed at the LVR-15 nuclear research reactor. The model for the design of calculations and experiments is based on the operation and properties of the VVER 1000 nuclear power plants, especially the type of fuel, vessel construction, and biological shielding. The corium simulating samples with different

Název v anglickém jazyce

Research of dosimetric characteristics of fuel containing material

Popis výsledku anglicky

In case of serious nuclear reactor accident the molten fuel can melt through the reactor containment and radioactive material can escape into the environment. A core-catcher filled with a sacrificial material is suggested under the reactor vessel to prevent such release of radioactivity. The sacrificial material should fix up thermal and chemical stabilization of the melt and prevent the creation of undesirable aerosols during the following years. This paper estimates the absorbed dose in hypothetical material for different types of radiation. The main part of the dose comes from alpha, beta and gamma radiation. Based on the estimates and calculations the irradiation experiments were designed at the LVR-15 nuclear research reactor. The model for the design of calculations and experiments is based on the operation and properties of the VVER 1000 nuclear power plants, especially the type of fuel, vessel construction, and biological shielding. The corium simulating samples with different

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název statě ve sborníku

RAD Proceedings

ISBN

978-86-80300-01-6

ISSN

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e-ISSN

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Počet stran výsledku

3

Strana od-do

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Název nakladatele

RAD Association

Místo vydání

Niš, Serbia

Místo konání akce

Budva, Montenegro

Datum konání akce

1. 1. 2015

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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