European Project ?Supercritical Water Reactor?Fuel Qualification Test?: Overview, Results, Lessons Learned, and Future Outlook

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001097" target="_blank" >RIV/26722445:_____/15:#0001097 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1115/1.4031034" target="_blank" >http://dx.doi.org/10.1115/1.4031034</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/1.4031034" target="_blank" >10.1115/1.4031034</a>

Jazyk výsledku

angličtina

Název v původním jazyce

European Project ?Supercritical Water Reactor?Fuel Qualification Test?: Overview, Results, Lessons Learned, and Future Outlook

Popis výsledku v původním jazyce

The supercritical water reactor (SCWR) is one of the six reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). One of the major challenges in the development of a SCWR is to develop materials for the fueland core structures that will be sufficiently corrosion resistant to withstand supercritical water conditions and to gain thermal-hydraulic experimental data that could be used for further improvement of heat transfer predictions in the supercritical region by numerical codes. Previously, core, reactor, and plant design concepts of the European high-performance light water reactor (HPLWR) have been worked out in great detail. As the next step, it has been proposed to carry out a fuel qualification test(FQT) of a small-scale fuel assembly in a research reactor under typical prototype conditions. Design and licensing of an experimental facility for the FQT, including the small-scale fuel assembly, the required coolant loop with supercri

Název v anglickém jazyce

European Project ?Supercritical Water Reactor?Fuel Qualification Test?: Overview, Results, Lessons Learned, and Future Outlook

Popis výsledku anglicky

The supercritical water reactor (SCWR) is one of the six reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). One of the major challenges in the development of a SCWR is to develop materials for the fueland core structures that will be sufficiently corrosion resistant to withstand supercritical water conditions and to gain thermal-hydraulic experimental data that could be used for further improvement of heat transfer predictions in the supercritical region by numerical codes. Previously, core, reactor, and plant design concepts of the European high-performance light water reactor (HPLWR) have been worked out in great detail. As the next step, it has been proposed to carry out a fuel qualification test(FQT) of a small-scale fuel assembly in a research reactor under typical prototype conditions. Design and licensing of an experimental facility for the FQT, including the small-scale fuel assembly, the required coolant loop with supercri

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Udržitelná energetika</a><br>

Návaznosti

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

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název periodika

Journal of Nuclear Engineering and Radiation Science

ISSN

2332-8983

e-ISSN

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Svazek periodika

2

Číslo periodika v rámci svazku

1

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

10

Strana od-do

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Kód UT WoS článku

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EID výsledku v databázi Scopus

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