Microstructural and mechanical property characterization of high-density uranium fuel for light water reactors

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000073" target="_blank" >RIV/26722445:_____/25:N0000073 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/25:00389098

Výsledek na webu

<a href="https://www.ojs.cvut.cz/ojs/index.php/APP/article/view/11140" target="_blank" >https://www.ojs.cvut.cz/ojs/index.php/APP/article/view/11140</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.14311/APP.2025.55.0041" target="_blank" >10.14311/APP.2025.55.0041</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Microstructural and mechanical property characterization of high-density uranium fuel for light water reactors

Popis výsledku v původním jazyce

One of the key concepts in the development of accident-tolerant fuels (ATFs) involves the use of high-density fuels, aimed at improving the safety and economics of light-water reactors. This work focuses on the microstructural and mechanical characterization of experimentally fabricated segments of dispersion-type high-density uranium fuels with a zirconium matrix and Zr-based cladding, intended for future testing in research reactors. Both U-Mo alloys and pure uranium metal were investigated, with particular attention given to the influence of thermal treatment on the phase composition and microstructure of the fuel segments. In addition, changes resulting from thermal exposure were evaluated. The research includes the identification of newly formed phases during transient conditions and the analysis of diffusion phenomena in the material. Mechanical properties were evaluated through microhardness measurements, and the results will serve as input parameters for computational simulations using the Serpent code to support the introduction of these fuels in the VR-2 research reactor.

Název v anglickém jazyce

Microstructural and mechanical property characterization of high-density uranium fuel for light water reactors

Popis výsledku anglicky

One of the key concepts in the development of accident-tolerant fuels (ATFs) involves the use of high-density fuels, aimed at improving the safety and economics of light-water reactors. This work focuses on the microstructural and mechanical characterization of experimentally fabricated segments of dispersion-type high-density uranium fuels with a zirconium matrix and Zr-based cladding, intended for future testing in research reactors. Both U-Mo alloys and pure uranium metal were investigated, with particular attention given to the influence of thermal treatment on the phase composition and microstructure of the fuel segments. In addition, changes resulting from thermal exposure were evaluated. The research includes the identification of newly formed phases during transient conditions and the analysis of diffusion phenomena in the material. Mechanical properties were evaluated through microhardness measurements, and the results will serve as input parameters for computational simulations using the Serpent code to support the introduction of these fuels in the VR-2 research reactor.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

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

Projekt

<a href="/cs/project/TN02000012" target="_blank" >TN02000012: Centrum pokročilých jaderných technologií II</a><br>

Návaznosti

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

Rok uplatnění

2025

Kód důvěrnosti údajů

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

Název statě ve sborníku

Acta Polytechnica CTU Proceedings, vol. 55

ISBN

978-800107515-9

ISSN

2336-5382

e-ISSN

—

Počet stran výsledku

8

Strana od-do

41-48

Název nakladatele

Czech Technical University in Prague

Místo vydání

Praha

Místo konání akce

Praha

Datum konání akce

17. 6. 2025

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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