Warm pre-stressing tests for WWER 440 reactor pressure vessel material

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F10%3A%230000745" target="_blank" >RIV/26722445:_____/10:#0000745 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/46356088:_____/10:#0001687

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Warm pre-stressing tests for WWER 440 reactor pressure vessel material

Popis výsledku v původním jazyce

During years 2006 - 2008, warm pre-stressing tests on small (Charpy size) and IT CT specimens were performed at NRI Rez. The specimens were made from WWER 440 reactor pressure vessel material in as-received, thermally treated (artificially aged) and irradiated conditions, the last two conditions simulating the end of life state of the RPV. In this paper, only results of tests performed for this material in as-received and irradiated conditions are presented. Evaluation of WPS tests was performed with using Chell and Wallin predictive models. The attention was paid to 5% probability level fracture predictions, since this level of probability is important for WPS application in pressurized thermal shock evaluation performed within the RPV integrity assessment. From point of view of this 5% probability fracture prediction, both Chell and Wallin models appeared not to be sufficiently conservative for LCF regime (prediction of "Case 2"); for other regimes (LUCF, LPUCF, LTUF and LPTUF) they

Název v anglickém jazyce

Warm pre-stressing tests for WWER 440 reactor pressure vessel material

Popis výsledku anglicky

During years 2006 - 2008, warm pre-stressing tests on small (Charpy size) and IT CT specimens were performed at NRI Rez. The specimens were made from WWER 440 reactor pressure vessel material in as-received, thermally treated (artificially aged) and irradiated conditions, the last two conditions simulating the end of life state of the RPV. In this paper, only results of tests performed for this material in as-received and irradiated conditions are presented. Evaluation of WPS tests was performed with using Chell and Wallin predictive models. The attention was paid to 5% probability level fracture predictions, since this level of probability is important for WPS application in pressurized thermal shock evaluation performed within the RPV integrity assessment. From point of view of this 5% probability fracture prediction, both Chell and Wallin models appeared not to be sufficiently conservative for LCF regime (prediction of "Case 2"); for other regimes (LUCF, LPUCF, LTUF and LPTUF) they

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

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Návaznosti

Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2010

Kód důvěrnosti údajů

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

Název statě ve sborníku

ASME pressure vessels and piping conference 2009, Vol 3: design and analysis

ISBN

978-0-7918-4366-6

ISSN

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e-ISSN

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Počet stran výsledku

12

Strana od-do

309-320

Název nakladatele

ASME

Místo vydání

New York, USA

Místo konání akce

Praha

Datum konání akce

1. 1. 2009

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000282619600036