Comparison of pts guides for reactor pressure vessel integrity assessment
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F13%3A%230000807" target="_blank" >RIV/26722445:_____/13:#0000807 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1115/PVP2013-97342" target="_blank" >http://dx.doi.org/10.1115/PVP2013-97342</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/PVP2013-97342" target="_blank" >10.1115/PVP2013-97342</a>
Alternative languages
Result language
angličtina
Original language name
Comparison of pts guides for reactor pressure vessel integrity assessment
Original language description
Integrity of reactor pressure vessels (RPV) are of the most importance for safety of the whole NPP. From all potential regimes, Pressurized Thermal Shock (PTS) regimes during emergency cooling conditions are the most severe and most important. Several nuclear codes are based in similar approaches but their procedures differ and are based on national knowledge and approach to fracture mechanics as well as non-destructive methods of reactor pressure vessel testing. The paper will compare requirements andprocedures for PTS evaluation in accordance with RCC-M code in France [2], KTA in Germany [3], Russian original code PNAEG from 1989 [5] and new procedure from 2004 for WWER vessels [4], as well as VERLIFE procedure and IAEA-NULIFE VERLIFE [6] procedurefor WWER RPVs and finally ASME Code requirements [1] including US NRC RG approach. Detailed comparison of individual parameters in calculations are compared - material properties, degradation of materials, calculated defects size and form
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
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Continuities
N - Vyzkumna aktivita podporovana z neverejnych zdroju
Others
Publication year
2013
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
2013 21st International Conference on Nuclear Engineering Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes Chengdu, China, July 29?August 2, 2013
ISBN
978-0-7918-5580-5
ISSN
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e-ISSN
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Number of pages
7
Pages from-to
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Publisher name
ASME
Place of publication
New York, USA
Event location
Chengdu, China
Event date
Jan 1, 2013
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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