Irradiaton of materials intended for chemical and thermal stabilization of molten nuclear fuel

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001082" target="_blank" >RIV/26722445:_____/15:#0001082 - 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

Irradiaton of materials intended for chemical and thermal stabilization of molten nuclear fuel

Popis výsledku v původním jazyce

Corium simulation samples with different composition of sacrificial material, uranium oxide, concrete fractions, and reactor vessel materials have been irradiated in the LVR-15 nuclear research reactor. Sacrificial material is used to control the properties of corium and to increase its cooling capacity. One of its most important characteristics should be the ability to create a solid that does not disintegrate and prevents release of dangerous and radioactive aerosols. A core catcher with this materialwould mitigate the impact of a serious accident and would allow easier disposal of damaged facilities. A calculation and experimental model is based on the operation and properties of VVER 1000 nuclear power plants, especially fuel type, vessel construction, and biological shielding. Two special capsules were developed for corium simulation sample irradiation. Samples in capsules were irradiated without and with thermal neutron shielding (e.g. cadmium). The size of the samples was very

Název v anglickém jazyce

Irradiaton of materials intended for chemical and thermal stabilization of molten nuclear fuel

Popis výsledku anglicky

Corium simulation samples with different composition of sacrificial material, uranium oxide, concrete fractions, and reactor vessel materials have been irradiated in the LVR-15 nuclear research reactor. Sacrificial material is used to control the properties of corium and to increase its cooling capacity. One of its most important characteristics should be the ability to create a solid that does not disintegrate and prevents release of dangerous and radioactive aerosols. A core catcher with this materialwould mitigate the impact of a serious accident and would allow easier disposal of damaged facilities. A calculation and experimental model is based on the operation and properties of VVER 1000 nuclear power plants, especially fuel type, vessel construction, and biological shielding. Two special capsules were developed for corium simulation sample irradiation. Samples in capsules were irradiated without and with thermal neutron shielding (e.g. cadmium). The size of the samples was very

Druh

D - Stať ve sborníku

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

2015

Kód důvěrnosti údajů

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

Název statě ve sborníku

TopFuel - Reactor fuel performance 2015

ISBN

978-92-95064-23-2

ISSN

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e-ISSN

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Počet stran výsledku

6

Strana od-do

442-447

Název nakladatele

European Nuclear Society

Místo vydání

Brussels, Belgium

Místo konání akce

Zürich, Švýcarsko

Datum konání akce

1. 1. 2015

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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