Analyses of thermal annealing influence on WWER 440 reactor pressure vessel internals materials

Kód výsledku v 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>

Nalezeny alternativní kódy

RIV/68407700:21340/19:00339550

Výsledek na webu

<a href="http://www.tanger.cz" target="_blank" >http://www.tanger.cz</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Analyses of thermal annealing influence on WWER 440 reactor pressure vessel internals materials

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Analyses of thermal annealing influence on WWER 440 reactor pressure vessel internals materials

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20306 - Audio engineering, reliability analysis

Projekt

<a href="/cs/project/TH02020565" target="_blank" >TH02020565: Zajištění dlouhodobého provozu vnitřních částí tlakových nádob reaktorů jaderných elektráren</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2019

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

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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Počet stran výsledku

6

Strana od-do

787-792

Název nakladatele

Tanger, Ltd.

Místo vydání

Ostrava

Místo konání akce

Brno

Datum konání akce

22. 5. 2019

Typ akce podle státní příslušnosti

CST - Celostátní akce

Kód UT WoS článku

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