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

Result code in 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>
Alternative codes found
RIV/46356088:_____/10:#0001687
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Warm pre-stressing tests for WWER 440 reactor pressure vessel material
Original language description
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
Czech name
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Czech description
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Publication year
2010
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
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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Number of pages
12
Pages from-to
309-320
Publisher name
ASME
Place of publication
New York, USA
Event location
Praha
Event date
Jan 1, 2009
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
000282619600036

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