Different approaches to estimation of reactor pressure vessel material embrittlement
The surveillance test data for the nuclear power plant which is under operation in Ukraine have been used to estimate WWER-1000 reactor pressure vessel (RPV) material embrittlement. The beltline materials (base and weld metal) were characterized using Charpy impact and fracture toughness test method...
Main Authors: | V. M. Revka, L. I. Chyrko, Yu. V. Chaikovskiy, O. V. Trygubenko |
---|---|
Format: | Article |
Language: | English |
Published: |
Institute for Nuclear Research, National Academy of Sciences of Ukraine
2013-03-01
|
Series: | Âderna Fìzika ta Energetika |
Subjects: | |
Online Access: | http://jnpae.kinr.kiev.ua/14.1/Articles_PDF/jnpae-2013-14-0038-Revka.pdf |
Similar Items
-
Lateral expansion and impact toughness correlation of VVER-1000 reactor pressure vessel materials
by: O. V. Trygubenko
Published: (2014-12-01) -
Radiation embrittlement of reactor pressure vessel materials of Rivne NPP unit 1 due to re-irradiation after recovery annealing
by: M. G. Holiak, et al.
Published: (2019-09-01) -
Uncertainty determination of fast neutron fluence onto the WWER pressure vessel metal surveillance specimens
by: О. M. Pugach, et al.
Published: (2021-03-01) -
Sorting of surveillance specimen halves relative to their location in the VVER-1000 reactor under irradiation
by: Yu. S. Gulchuk, et al.
Published: (2019-09-01) -
Weld metal irradiation embrittlement analysis in the range of over-design neutron fluences
by: L. I. Chyrko, et al.
Published: (2020-12-01)