Progress in Experimental Development of MSR and FHR Technologies

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26316919%3A_____%2F18%3AN0000036" target="_blank" >RIV/26316919:_____/18:N0000036 - isvavai.cz</a>

Alternative codes found

RIV/26722445:_____/18:N0000088

Result on the web

<a href="http://ansannual.org/wp-content/2018/Data/pdfs/342-24570.pdf" target="_blank" >http://ansannual.org/wp-content/2018/Data/pdfs/342-24570.pdf</a>

DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Progress in Experimental Development of MSR and FHR Technologies

Original language description

A technology of nuclear reactor systems with liquid molten salt fuel has been investigated in the Czech Republic since 1999. After 2005, the studies cover also the areas of thorium – uranium fuel cycle technology, material research and development of selected components of the Molten Salt Reactor technology. An important milestone for further research was the year 2012, when a cooperation agreement (Memorandum of Understanding) on the development of MSR reactors was concluded between the Ministry of Industry and Trade and the US – Department of Energy. Under this agreement, ORNL has provided the UJV Řež and the Research Center Řež with the 7LiF-BeF2 fluoride salt (FLIBE) for research on neutron properties realized on LR-0 reactor in Řež. Today a new four years (2017 – 2020) project of MSR/FHR technology development is the key component of the Czech R&D program on fluoride salt-cooled nuclear reactor systems. The project is a follow-up and broadening of existing Czech activities in MSR. The aim of the project is to contribute to the development of MSR and FHR reactor technology in the area of reactor physics, nuclear – chemical engineering and material research. The project is solved by a consortium of Czech research institutions and industrial companies leaded by the Research Centre Řež.

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

20501 - Materials engineering

Project

<a href="/en/project/TH02020113" target="_blank" >TH02020113: Research and development of fluoride salt-cooled nuclear reactor systems</a><br>

Continuities

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

Publication year

2018

Confidentiality

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

Article name in the collection

Transactions of the American Nuclear Society

ISBN

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ISSN

0003-018X

e-ISSN

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Number of pages

2

Pages from-to

713-714

Publisher name

American Nuclear Society

Place of publication

Illinois

Event location

Philadelphia, Pennsylvania, USA

Event date

Jun 17, 2018

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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