Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23520%2F16%3A43928579" target="_blank" >RIV/49777513:23520/16:43928579 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1007/s00419-015-1053-0" target="_blank" >http://dx.doi.org/10.1007/s00419-015-1053-0</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1007/s00419-015-1053-0" target="_blank" >10.1007/s00419-015-1053-0</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods

Popis výsledku v původním jazyce

The paper deals with modelling of nonlinear flexural vibration of nuclear fuel rod in hexagonal-type nuclear fuel assembly. The fuel rods are transversally linked to each other by spacer grid cells to inside the fuel assembly skeleton in several level spacings. The main components of the fuel rods are cladding in the form of thin-walled tubes of zirconium and fuel pellet columns incorporated in-tube with radial clearance. The flexural fuel rod vibration, caused by the fuel assembly support plate motion in the reactor core, can exhibit impulse contact forces between fuel rod components and possible loss of contact between the fuel rod cladding and some of spacer grid cells. Dynamic forces transmitted between fuel rods and spacer grid cells are used for calculation of expected lifetime period of nuclear fuel assembly in terms of fuel rod cladding abrasion. The presented method introduces the first known approach to mathematical modelling of fuel rod nonlinear vibration and fretting wear varying during reactor operation.

Název v anglickém jazyce

Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods

Popis výsledku anglicky

The paper deals with modelling of nonlinear flexural vibration of nuclear fuel rod in hexagonal-type nuclear fuel assembly. The fuel rods are transversally linked to each other by spacer grid cells to inside the fuel assembly skeleton in several level spacings. The main components of the fuel rods are cladding in the form of thin-walled tubes of zirconium and fuel pellet columns incorporated in-tube with radial clearance. The flexural fuel rod vibration, caused by the fuel assembly support plate motion in the reactor core, can exhibit impulse contact forces between fuel rod components and possible loss of contact between the fuel rod cladding and some of spacer grid cells. Dynamic forces transmitted between fuel rods and spacer grid cells are used for calculation of expected lifetime period of nuclear fuel assembly in terms of fuel rod cladding abrasion. The presented method introduces the first known approach to mathematical modelling of fuel rod nonlinear vibration and fretting wear varying during reactor operation.

Druh

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

CEP obor

JR - Ostatní strojírenství

OECD FORD obor

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Projekt

<a href="/cs/project/ED1.1.00%2F02.0090" target="_blank" >ED1.1.00/02.0090: NTIS - Nové technologie pro informační společnost</a><br>

Návaznosti

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

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název periodika

ARCHIVE OF APPLIED MECHANICS

ISSN

0939-1533

e-ISSN

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Svazek periodika

86

Číslo periodika v rámci svazku

4

Stát vydavatele periodika

DE - Spolková republika Německo

Počet stran výsledku

12

Strana od-do

"657?668"

Kód UT WoS článku

000372292000005

EID výsledku v databázi Scopus

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