Research of dosimetric characteristics of fuel containing material

Result code in 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>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Research of dosimetric characteristics of fuel containing material
Original language description
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
Czech name
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Czech description
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Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year
2015
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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