Dose and temperature distribution in spent fuel containing material

Result code in 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>

Result on the web

<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>

Result language

angličtina

Original language name

Dose and temperature distribution in spent fuel containing material

Original language description

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.

Czech name

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Czech description

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Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

<a href="/en/project/LH12224" target="_blank" >LH12224: Modelling and investigation of non-standard situations of new type of nuclear reactors</a><br>

Continuities

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

Publication year

2016

Confidentiality

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

Name of the periodical

EPJ Nuclear Sciences & Technologies

ISSN

2491-9292

e-ISSN

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Volume of the periodical

2

Issue of the periodical within the volume

UNSP 31

Country of publishing house

FR - FRANCE

Number of pages

6

Pages from-to

1-6

UT code for WoS article

000384805800002

EID of the result in the Scopus database

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