Analyses of thermal annealing influence on WWER 440 reactor pressure vessel internals materials
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000025" target="_blank" >RIV/46356088:_____/19:N0000025 - isvavai.cz</a>
Alternative codes found
RIV/68407700:21340/19:00339550
Result on the web
<a href="http://www.tanger.cz" target="_blank" >http://www.tanger.cz</a>
DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Analyses of thermal annealing influence on WWER 440 reactor pressure vessel internals materials
Original language description
Thermal annealing is a proven material treatment method applicable to WWER type reactor pressure vessels with the aim of prolonging their operational lifetime. However, reactor pressure vessel internals of nuclear power plants are exposed to more severe operating conditions (high pressure and temperatures, higher neutron flux, corrosion environment), which cause gradual degradation of their mechanical properties. Thermal annealing can be one of the possible solutions to re-establish initial mechanical properties of reactor pressure vessel internals materials and thus can contribute to long term operation of nuclear power plants. This paper presents results of mechanical properties evaluation (especially hardness) of non-annealed and annealed state of material of WWER 440 - type reactor internals in initial un-irradiated conditions. Within the project an extensive program of experimental activities realized on un-irradiated materials in initial, work hardened, and annealed state was performed to create basis for further analyses on irradiated structural materials. As an integral part of experimental activities microstructural analyses were also incorporated to study of structural changes of non-annealed and annealed material. This paper includes results obtained within the project TH02020565 “Assurance of Safe and Long-Term Operation of Nuclear Pressure Vessel Internals” which is realized by ÚJV Řež, a. s. in cooperation with Czech Technical University in Prague, FNSPE, in the period from 2017 to 2020 with the support of Technology Agency of the Czech Republic.
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
20306 - Audio engineering, reliability analysis
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
2019
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 2019 - 28th International Conference on Metallurgy and Materials, Conference Proceedings
ISBN
978-808729492-5
ISSN
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e-ISSN
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Number of pages
6
Pages from-to
787-792
Publisher name
Tanger, Ltd.
Place of publication
Ostrava
Event location
Brno
Event date
May 22, 2019
Type of event by nationality
CST - Celostátní akce
UT code for WoS article
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