Model Materials for Reactor Pressure Vessel
J. Degmováa, L. Debarberisb and V. Kršjakb
aDepartment of Nuclear Physics and Technology, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology, Ilkovičova 3, 812 19 Bratislava, Slovakia
bJRC-IE, Joint Research Centre, Institute for Energy, P.O. Box 2, Petten 1755 ZG, The Netherlands
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In this paper we report preliminary results from a study focused on investigation of the role of elements as Cr, Ni, Mn and Si in the radiation stability of reactor pressure vessel steels. Twelve model ferritic steels and eight model welds with basic composition derived from Russian VVER-1000 and Western PWR reactor pressure vessel materials were studied by magnetic Barkhausen noise and Charpy-V impact measurements. Comparison of these two model materials led to the conclusion that the ductile-brittle transition temperatures and Barkhausen noise RMS values of model steels are shifted to the lower values as those of model welds. The VVER-1000 as reference point is shifted to lower RMS values in comparison with model steels and model welds. The next stage of the assessment will involve the investigation of the radiation effect on the model steels with accumulated neutron fluence of 1019 n/cm2.
DOI: 10.12693/APhysPolA.118.1054
PACS numbers: 28.41.Qb, 62.25.Mn, 75.50.Cc, 81.70.Bt, 81.70.Ex