Thermal Annealing of WWER – 440 Nuclear Reactor Pressure Vessel Internals Material
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F20%3AN0000011" target="_blank" >RIV/46356088:_____/20:N0000011 - isvavai.cz</a>
Alternative codes found
RIV/68407700:21340/20:00344893
Result on the web
<a href="https://www.confer.cz/proceedings/metal/2020.pdf" target="_blank" >https://www.confer.cz/proceedings/metal/2020.pdf</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.37904/metal.2020.3497" target="_blank" >10.37904/metal.2020.3497</a>
Alternative languages
Result language
angličtina
Original language name
Thermal Annealing of WWER – 440 Nuclear Reactor Pressure Vessel Internals Material
Original language description
Current trend of long-term operation of NPP’s for more than 60 years requires assurance of its safety and reliability. One of the solutions how to extend service life of reactor pressure vessel (RPV) is thermal annealing, which became a verified technology and its application in nuclear industry was prompted mainly due to an inability of RPV exchange. At present time, there is no comparable method for RPV internals that are not monitored by surveillance program and their material is exposed to significantly more intense neutron flux than the RPV. Paper presents the thermal annealing as one of the possible solutions to provide and re-establish sufficient mechanical properties of RPV internals during the operation. According to previously obtained results of unirradiated material, two thermal annealing regimes for irradiated experimental material were selected - based on the annealing temperatures of 550 and 600 °C. The possibility of recovery of mechanical properties to the level almost corresponding to the initial state by the thermal annealing was studied by hardness testing and static fracture toughness tests before and after the thermal annealing of irradiated material.
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TH02020565" target="_blank" >TH02020565: Assurance of Safe and Long Term Operation of Nuclear Reactor Pressure Vessel Internals</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2020
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
Metal 2000 : 29th International Conference on Metallurgy and Materials : Conference Proceedings
ISBN
978-80-87294-97-0
ISSN
2694-9296
e-ISSN
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Number of pages
6
Pages from-to
416-421
Publisher name
Tanger,
Place of publication
Brno
Event location
Brno
Event date
May 20, 2020
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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