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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

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • 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

  • 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