All

What are you looking for?

All
Projects
Results
Organizations

Quick search

  • Projects supported by TA ČR
  • Excellent projects
  • Projects with the highest public support
  • Current projects

Smart search

  • That is how I find a specific +word
  • That is how I leave the -word out of the results
  • “That is how I can find the whole phrase”

Thermal annealing of WWER-440 nuclear reactor pressure vessel internals: Present status

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F18%3AN0000039" target="_blank" >RIV/46356088:_____/18:N0000039 - isvavai.cz</a>

  • Result on the web

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    angličtina

  • Original language name

    Thermal annealing of WWER-440 nuclear reactor pressure vessel internals: Present status

  • Original language description

    Reactor pressure vessel (RPV) of light water reactor and its internals are the most important components of any nuclear power plant. RPV and its internals are exposed to high temperatures, pressures and intensive neutron flux during the operation. These conditions lead up to material degradation - especially radiation hardening and embrittlement. Paper presents the annealing treatment as one of the possible solutions to provide and re-establish sufficient mechanical properties of RPV internals during the operation. The first part of the poster is dedicated to the description of equipment which is used for the annealing of unirradiated and irradiated materials at the UJV Rez hot cell facility. Following part shows selection of unirradiated material for definition of original mechanical properties. Next part is an overview of selected annealing regimes. The main section is focused on definition of mechanical properties (especially hardness) of original and annealed material of WWER 440 type reactor internals as well as on methods and analyses employed to study of mechanical properties changes. The final part discusses the next planned steps in the solution of the research project TH02020565: "Assurance of Safe and Long Term Operation of Nuclear Reactor Pressure Vessel Internals" which is realized in the period from 2016 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

    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

    2018

  • 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 2018 - 27th International Conference on Metallurgy and Materials, Conference Proceedings

  • ISBN

    978-808729484-0

  • ISSN

  • e-ISSN

  • Number of pages

    5

  • Pages from-to

    658-662

  • Publisher name

    TANGER Ltd.

  • Place of publication

  • Event location

    Brno

  • Event date

    May 23, 2018

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article