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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

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

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • 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

  • e-ISSN

  • 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