Irradiation Embrittlement Monitoring Procedures and Results of Reactor Pressure Vessels WWER Type
This paper describes part of a knowledge preservation programme
coordinated by JRC Petten. The following issues are discussed and analysed:
comparison of surveillance specimen results from WWER-440 and 1000 units;
surveillance specimen programme modernisation based on the new philosophy
and approaches; the efficiency of Reactor Pressure Vessel (RPV) steel annealing
by implementation of procedures such as boat sampling, instrumented hardness,
neutron diffraction, positron annihilation, etc.; the analyses of irradiated
samples from RPV materials by modern methods; the irradiation embrittlement
of the RPV weld metal due to the effects of impurities; the evaluation of RPV
irradiation embrittlement trends during planned LTO; critical analyses of
existing rules and codes, used by lifetime evaluation; theoretical models which
may more or less describe the influence of impurities in RPV steels; evaluation
of impact and toughness test results by implementation of the ‘master curve
approach’.
KUPCA Ludovit;
VON ESTORFF Ulrik;
2012-02-03
Inderscience
JRC59467
1479-540X (print),
1479-5418 (online),
http://www.inderscience.com/browse/index.php?journalID=92&year=2010&vol=4&issue=3,
https://publications.jrc.ec.europa.eu/repository/handle/JRC59467,
10.1504/IJNKM.2010.036912,
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