Irradiation-assisted stress corrosion cracking of Ti-stabilized austenitic stainless steel

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000023" target="_blank" >RIV/46356088:_____/19:N0000023 - isvavai.cz</a>
Result on the web
<a href="http://www.ans.org/store/item-700430/" target="_blank" >http://www.ans.org/store/item-700430/</a>
DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Irradiation-assisted stress corrosion cracking of Ti-stabilized austenitic stainless steel
Original language description
IASCC has been widely observed in reactor vessel internals (RVI) in BWRs and pressurized water PWRs of the western type. In the eastern type of PWRs, also called WWERs, IASCC has been reported in only a few cases. The main differences between the PWRs of western and eastern designs are the construction materials of RVI (Type 321 in WWERs) and the operational environment. New crack growth disposition curves for RVI materials in PWR of western type (the proposed 75th percentile PWR curve in the ASME Section XI Code Case N-889, and the PWR mean curve) were used to verify the curves applicability also for RVI materials in WWERs.
Czech name
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Czech description
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Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
Nineteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
ISBN
978-0-89448-765-1
ISSN
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e-ISSN
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Number of pages
7
Pages from-to
1268-1274
Publisher name
American Nuclear Society
Place of publication
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Event location
Boston, USA
Event date
Aug 18, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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