Dose and temperature distribution in spent fuel containing material

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000013" target="_blank" >RIV/26722445:_____/16:N0000013 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1051/epjn/2016024" target="_blank" >http://dx.doi.org/10.1051/epjn/2016024</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1051/epjn/2016024" target="_blank" >10.1051/epjn/2016024</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Dose and temperature distribution in spent fuel containing material

Popis výsledku v původním jazyce

Spent fuel containing material (SFCM) can arise during severe nuclear reactor accident by melting of a reactor core and surrounding material (corium) or during accident in spent fuel storage. It consists of nuclear fuel, fission products, activation products and materials from fuel cladding, concrete, etc. The paper deals with dose and temperature characteristics inside the SFCM after transition of the molten mixture to solid state. Calculations were made on simplified spherical models, without connection to some specific nuclear accident. The dose rate was estimated for alpha, beta and gamma radiation in times over the course of 30 years from the end of the fission chain reaction. Concentration of helium generated in the material by alpha decay was calculated. For the dose rate values estimation, computation code ORIGEN 2.2 with dosimetric library ENDF/B-IV were used. Temperature distribution inside the solid SFCM was calculated by FLUENT code. As source of heating, energy of radioactive decays was taken. Estimated dose and temperature characteristics can be used, e.g. for evaluation of radiation damage and temperature behaviour of SFCM or for radiation test design of corium simulating materials.

Název v anglickém jazyce

Dose and temperature distribution in spent fuel containing material

Popis výsledku anglicky

Spent fuel containing material (SFCM) can arise during severe nuclear reactor accident by melting of a reactor core and surrounding material (corium) or during accident in spent fuel storage. It consists of nuclear fuel, fission products, activation products and materials from fuel cladding, concrete, etc. The paper deals with dose and temperature characteristics inside the SFCM after transition of the molten mixture to solid state. Calculations were made on simplified spherical models, without connection to some specific nuclear accident. The dose rate was estimated for alpha, beta and gamma radiation in times over the course of 30 years from the end of the fission chain reaction. Concentration of helium generated in the material by alpha decay was calculated. For the dose rate values estimation, computation code ORIGEN 2.2 with dosimetric library ENDF/B-IV were used. Temperature distribution inside the solid SFCM was calculated by FLUENT code. As source of heating, energy of radioactive decays was taken. Estimated dose and temperature characteristics can be used, e.g. for evaluation of radiation damage and temperature behaviour of SFCM or for radiation test design of corium simulating materials.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

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

2016

Kód důvěrnosti údajů

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

Název periodika

EPJ Nuclear Sciences & Technologies

ISSN

2491-9292

e-ISSN

—

Svazek periodika

2

Číslo periodika v rámci svazku

UNSP 31

Stát vydavatele periodika

FR - Francouzská republika

Počet stran výsledku

6

Strana od-do

1-6

Kód UT WoS článku

000384805800002

EID výsledku v databázi Scopus

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