Study of natural uranium fuel for a new reactor design TEPLATOR

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F21%3A43966458" target="_blank" >RIV/49777513:23220/21:43966458 - isvavai.cz</a>

Result on the web

<a href="https://www.epj-conferences.org/articles/epjconf/abs/2021/07/epjconf_animma2021_07012/epjconf_animma2021_07012.html" target="_blank" >https://www.epj-conferences.org/articles/epjconf/abs/2021/07/epjconf_animma2021_07012/epjconf_animma2021_07012.html</a>

DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Study of natural uranium fuel for a new reactor design TEPLATOR

Original language description

The TEPLATOR is a new type of nuclear reactor which the main purpose is producing heat for district heating. It is designed as a special thermal reactor with 55 fuel channels for fuel assemblies, which is moderated and cooled by heavy water and operated around atmospheric pressure. The TEPLATOR DEMO is designed for the use of irradiated fuel from PWR or BWR reactors. Using heavywater as the moderator and coolant in this reactor concept allows to use natural uranium as an alternative fuel in case that the irradiated fuel is not available for some reason. This solution is suitable because of the price of natural uranium and the absence of costly fuel enrichment. This article is focused on deeper analyses of alternative suitable fuel for TEPLATOR based on natural uranium and new fuel geometries. This work builds on previous research on alternative fuel material and geometry for the TEPLATOR. It is mainly concerned with the neutronic development of fuel assemblies, the possibility of manufacturing of developed fuel types, and optimization of fuel management and uranium consumption. This article contains predetermined candidates for suitable fuel geometries and new untested fuel geometry types with some new advantages. Finally, optimization of the whole reactor core and number of fuel channels was made in terms of increased safety and higher fuel burn-up. Presented calculations were performed by Monte Carlo code Seprent.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

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Continuities

S - Specificky vyzkum na vysokych skolach

Publication year

2021

Confidentiality

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

Article name in the collection

EPJ Web of Conferences

ISBN

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ISSN

2100-014X

e-ISSN

2100-014X

Number of pages

5

Pages from-to

1-5

Publisher name

EDP Sciences

Place of publication

Praha

Event location

Praha, Czech republic

Event date

Jun 21, 2021

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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