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

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

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

Projekt

<a href="/cs/project/LO1506" target="_blank" >LO1506: Podpora udržitelnosti centra NTIS - Nové technologie pro informační společnost</a><br>

Návaznosti

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

Rok uplatnění

2018

Kód důvěrnosti údajů

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

Název periodika

PROGRESS IN NUCLEAR ENERGY

ISSN

0149-1970

e-ISSN

—

Svazek periodika

108

Číslo periodika v rámci svazku

September 2018

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

9

Strana od-do

160-168

Kód UT WoS článku

000442979400017

EID výsledku v databázi Scopus

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