All

What are you looking for?

All
Projects
Results
Organizations

Quick search

  • Projects supported by TA ČR
  • Excellent projects
  • Projects with the highest public support
  • Current projects

Smart search

  • That is how I find a specific +word
  • That is how I leave the -word out of the results
  • “That is how I can find the whole phrase”

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

The result's identifiers

  • Result code in 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>

  • Alternative codes found

    RIV/68407700:21340/25:00389098

  • Result on the web

    <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>

Alternative languages

  • Result language

    angličtina

  • Original language name

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

  • Original language description

    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.

  • Czech name

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

    <a href="/en/project/TN02000012" target="_blank" >TN02000012: Center of Advanced Nuclear Technology II</a><br>

  • Continuities

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

Others

  • Publication year

    2025

  • Confidentiality

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

Data specific for result type

  • Article name in the collection

    Acta Polytechnica CTU Proceedings, vol. 55

  • ISBN

    978-800107515-9

  • ISSN

    2336-5382

  • e-ISSN

  • Number of pages

    8

  • Pages from-to

    41-48

  • Publisher name

    Czech Technical University in Prague

  • Place of publication

    Praha

  • Event location

    Praha

  • Event date

    Jun 17, 2025

  • Type of event by nationality

    EUR - Evropská akce

  • UT code for WoS article