Experimental and Analytical Tools for Safety Research of GEN IV Reactors

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000059" target="_blank" >RIV/26722445:_____/18:N0000059 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.kernd.de/kernd-en/fachzeitschrift-atw/" target="_blank" >https://www.kernd.de/kernd-en/fachzeitschrift-atw/</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Experimental and Analytical Tools for Safety Research of GEN IV Reactors

Popis výsledku v původním jazyce

Current research on nuclear safety in the world, in addition to supporting existing nuclear power plants (PLEX, mitigation of severe accidents, the development of accident tolerant fuel, decommissioning, etc.), is focused on the more detailed aspects of the new reactors. The new generation reactors are expected inter alia to use innovative types of fuel and new types of coolants, such as e.g. Super-Critical Water (SCW), supercritical CO2, liquid metals, fluoride salts or high-temperature Helium. The paper will describe new experimental infrastructure build recently in Research Centre Rez under the SUSEN (Sustainable Energy) project and available analytical tools for supporting safety research of GEN IV reactors. Two experimental loops - SCWL (Supercritical Water Loop) and HTHL (High Temperature Helium Loop) will serve as in-pile loops in the active core of the research reactor LVR-15. The loops insertion in the reactor LVR-15 requires performing additional safety analyses studying the mutual interference of the loops and the reactor, especially in conditions of abnormal operation or accident conditions of the loops. The paper will provide examples of these analyses made using codes ATHLET (supercritical water) and TRACE (high temperature He) illustrating process of their assessment and practical use. These activities provide significant opportunity for TSO team in building its new competencies.

Název v anglickém jazyce

Experimental and Analytical Tools for Safety Research of GEN IV Reactors

Popis výsledku anglicky

Current research on nuclear safety in the world, in addition to supporting existing nuclear power plants (PLEX, mitigation of severe accidents, the development of accident tolerant fuel, decommissioning, etc.), is focused on the more detailed aspects of the new reactors. The new generation reactors are expected inter alia to use innovative types of fuel and new types of coolants, such as e.g. Super-Critical Water (SCW), supercritical CO2, liquid metals, fluoride salts or high-temperature Helium. The paper will describe new experimental infrastructure build recently in Research Centre Rez under the SUSEN (Sustainable Energy) project and available analytical tools for supporting safety research of GEN IV reactors. Two experimental loops - SCWL (Supercritical Water Loop) and HTHL (High Temperature Helium Loop) will serve as in-pile loops in the active core of the research reactor LVR-15. The loops insertion in the reactor LVR-15 requires performing additional safety analyses studying the mutual interference of the loops and the reactor, especially in conditions of abnormal operation or accident conditions of the loops. The paper will provide examples of these analyses made using codes ATHLET (supercritical water) and TRACE (high temperature He) illustrating process of their assessment and practical use. These activities provide significant opportunity for TSO team in building its new competencies.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

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OECD FORD obor

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

Projekt

<a href="/cs/project/EF15_008%2F0000293" target="_blank" >EF15_008/0000293: Udržitelná energetika (SUSEN) - 2. fáze</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2018

Kód důvěrnosti údajů

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

Název periodika

ATW - International Journal for nuclear power

ISSN

1431-5254

e-ISSN

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Svazek periodika

63

Číslo periodika v rámci svazku

4

Stát vydavatele periodika

DE - Spolková republika Německo

Počet stran výsledku

6

Strana od-do

221-226

Kód UT WoS článku

000430246500005

EID výsledku v databázi Scopus

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