Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F13%3A%230000780" target="_blank" >RIV/26722445:_____/13:#0000780 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.5006/0803" target="_blank" >http://dx.doi.org/10.5006/0803</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.5006/0803" target="_blank" >10.5006/0803</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension

Popis výsledku v původním jazyce

The paper aims to give a present status of knowledge on irradiation-assisted stress corrosion cracking (IASCC) from the point of view of nuclear power plant life extension. Field experience as well as laboratory test results are considered to illustratehow IASCC already impacts plant operation. IASCC has been differentiated with difficulty from standard integranular stress corrosion cracking (IGSCC), but above a threshold radiation dose, an enhanced portion of intergranular fracture are convincing evidences for IASCC. IASCC cracking in boiling water reactor (BWR) core shrouds started wide studies of materials of irradiated reactor internals. The last cases of IASCC have been found in pressurized water reactor/water-water energy reactor (PWR/WWER) baffle bolts. Laboratory slow strain rate tests as well as constant load and crack growth rate tests in simulated BWR and PWR environments resulted in the discovery of the IASCC threshold dose, the threshold stress, and that the cracking kine

Název v anglickém jazyce

Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension

Popis výsledku anglicky

The paper aims to give a present status of knowledge on irradiation-assisted stress corrosion cracking (IASCC) from the point of view of nuclear power plant life extension. Field experience as well as laboratory test results are considered to illustratehow IASCC already impacts plant operation. IASCC has been differentiated with difficulty from standard integranular stress corrosion cracking (IGSCC), but above a threshold radiation dose, an enhanced portion of intergranular fracture are convincing evidences for IASCC. IASCC cracking in boiling water reactor (BWR) core shrouds started wide studies of materials of irradiated reactor internals. The last cases of IASCC have been found in pressurized water reactor/water-water energy reactor (PWR/WWER) baffle bolts. Laboratory slow strain rate tests as well as constant load and crack growth rate tests in simulated BWR and PWR environments resulted in the discovery of the IASCC threshold dose, the threshold stress, and that the cracking kine

Druh

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

CEP obor

JL - Únava materiálu a lomová mechanika

OECD FORD obor

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Projekt

<a href="/cs/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Udržitelná energetika</a><br>

Návaznosti

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

Rok uplatnění

2013

Kód důvěrnosti údajů

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

Název periodika

Corrosion

ISSN

0010-9312

e-ISSN

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Svazek periodika

69

Číslo periodika v rámci svazku

10

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

11

Strana od-do

964-974

Kód UT WoS článku

000324997100003

EID výsledku v databázi Scopus

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