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Evolution of grid-to-rod fretting of nuclear fuel rods during burnup

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23520%2F18%3A43951258" target="_blank" >RIV/49777513:23520/18:43951258 - isvavai.cz</a>

  • Result on the web

    <a href="http://dx.doi.org/10.1016/j.pnucene.2018.05.016" target="_blank" >http://dx.doi.org/10.1016/j.pnucene.2018.05.016</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.pnucene.2018.05.016" target="_blank" >10.1016/j.pnucene.2018.05.016</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Evolution of grid-to-rod fretting of nuclear fuel rods during burnup

  • Original language description

    Nuclear fuel rod consists of the cladding and fuel pellets stack. Fuel rods are mounted in fuel assemblies and they are linked by spacer grids. Due to vibration of a fuel assembly during the reactor operation, grid-to-rod fretting (GTRF) occurs in contact points between the cladding of the fuel rod and spacer grid cells. The GTRF phenomenon causes the loss of mass of the cladding in contact points and it can possibly lead to leakage of fission products into a coolant. The paper presents a complex modelling concept for the GTRF analysis of fuel rods due to vibration caused by pressure pulsations of the coolant. The method deals with several essential subproblems. The key part of the method is a dynamic model that simulates vibration of the fuel rod. To estimate wear properties of the cladding, an experimental procedure is used and to determine the state of burnup, a physical model is used. Based on the simulated vibration of the fuel rod and the subsequent GTRF analysis, the evolution of the GTRF during burnup can be determined.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

    <a href="/en/project/LO1506" target="_blank" >LO1506: Sustainability support of the centre NTIS - New Technologies for the Information Society</a><br>

  • Continuities

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

Others

  • Publication year

    2018

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    PROGRESS IN NUCLEAR ENERGY

  • ISSN

    0149-1970

  • e-ISSN

  • Volume of the periodical

    108

  • Issue of the periodical within the volume

    September 2018

  • Country of publishing house

    NL - THE KINGDOM OF THE NETHERLANDS

  • Number of pages

    9

  • Pages from-to

    160-168

  • UT code for WoS article

    000442979400017

  • EID of the result in the Scopus database