PROGRESS IN ALLEGRO THERMAL-HYDRAULICS RELATED RESEARCH AND DEVELOPMENT
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F22%3A00374644" target="_blank" >RIV/68407700:21220/22:00374644 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
PROGRESS IN ALLEGRO THERMAL-HYDRAULICS RELATED RESEARCH AND DEVELOPMENT
Original language description
Recent progress in research and development concerning thermal-hydraulics and related topics focused on the ALLEGRO reactor is presented in this paper. ALLEGRO is a concept of a demonstration unit of the Gas-cooled Fast Reactor (GFR) technology, its main goals being technology demonstration, qualification of innovative fuel materials, and proof of safety concept of GFR in general, since no reactor of this type has ever been operated so far. The presented work focuses mainly on description of ongoing national R&D projects and activities of V4G4 Centre of Excellence, their main goals, results and their position within GFR research in Europe. It includes an overview of experimental work that has been carried out on two state-of-the-art facilities dedicated to thermal-hydraulics research, as well as safety development of high-temperature gas-cooled reactors – the S-ALLEGRO integral facility in Czech Republic, and STU helium loop in Slovakia. A new concept of decay heat removal system for ALLEGRO is described, with computational analysis comparing its effectiveness in transients with the current design. The described activities include also development of computational tools in form of coupled thermal-hydraulics-3D reactor physics modelling for analyses of unprotected and reactivity induced accidents. Last but not least, a new concept of a safety system for GFR, based on prolongated rundown of the main blower(s), is described.
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TK01030116" target="_blank" >TK01030116: Conceptual design of safety-important components of helium-cooled fast demonstration reactor ALLEGRO</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2022
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
ISBN
9789076971261
ISSN
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e-ISSN
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Number of pages
14
Pages from-to
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Publisher name
American Nuclear Society, Inc.
Place of publication
Illinois
Event location
Brussel
Event date
Mar 6, 2022
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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