Title: Irradiation embrittlement monitoring procedures and results of reactor pressure vessels of the WWER type
Authors: Ludovit Kupca
Addresses: Structural Analysis Department, Division of NPP Diagnostic, VUJE Inc., Okruzna 5, 918 64 Trnava, Slovak Republic
Abstract: 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|.
Keywords: nuclear knowledge preservation; surveillance specimen programme; WWER 440 units; WWER 1000 units; databases; annealing; RPV steel; reactor pressure vessels; water chemistry; cladding; fracture toughness; embrittlement modelling; irradiation embrittlement; embrittlement monitoring; nuclear knowledge management.
International Journal of Nuclear Knowledge Management, 2010 Vol.4 No.3, pp.243 - 263
Published online: 16 Nov 2010 *Full-text access for editors Access for subscribers Purchase this article Comment on this article