In order to assess the validity of post-irradiation annealing as a method to predict results of high temperature irradiation a new analysis of experimental data has been performed revealing the combined influence of annealing temperature and impurities content on residual embrittlement after annealing. For 2CrMoV (WWER-440 reactor pressure vessel) steel with low contents of copper and phosphorus, the comparison of two embrittlement dependencies has been done: on irradiation temperature and postirradiation annealing temperature. It is demonstrated that data for both the transition temperature shift after irradiation, DTk, and the residual transition temperature shift after post-irradiation annealing, DTres, fall within the same scatter band....
It is believed that in the next decade or so, several nuclear reactor pressure vessels (RPVs) may ex...
The results of long term research programme concerning the determination of irradiation embrittlemen...
Re-irradiation data available in RRC-KI and in Fortum Engineering /VTT is analysed in order to ident...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The reactor pressure vessel (RPV) surrounding the core of a commercial nuclear power plant is subjec...
The transition temperature shift recovery efficiency after annealing (475оС, 100 hours) in dependenc...
One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPVS) is to t...
Irradiation embrittlement rate as well as the re-embrittlement rate after annealing of pressure vess...
A comparison between pearlitic 2CrMoV steel (WWER-440) and 9% Cr based ferritic-martensitic steels (...
One of the options to mitigate the effects of irradiation on reactor pressure vessels is to thermall...
Surveillance specimens of 15Kh2MFA reactor pressure vessel (RPV) steel and Sv-10KhMFT weld metal wer...
One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to th...
Surveillance specimens of 15Kh2MFA reactor pressure vessel (RPV) steel and Sv-10KhMFT weld metal wer...
The analysis of WWER-440 RPV welds mechanical properties and behaviour of nanoscale structural featu...
It is believed that in the next decade or so, several nuclear reactor pressure vessels (RPVs) may ex...
The results of long term research programme concerning the determination of irradiation embrittlemen...
Re-irradiation data available in RRC-KI and in Fortum Engineering /VTT is analysed in order to ident...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The dependence of the recovery of the transition temperature shift after annealing (475 °C, 100 h) o...
The reactor pressure vessel (RPV) surrounding the core of a commercial nuclear power plant is subjec...
The transition temperature shift recovery efficiency after annealing (475оС, 100 hours) in dependenc...
One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPVS) is to t...
Irradiation embrittlement rate as well as the re-embrittlement rate after annealing of pressure vess...
A comparison between pearlitic 2CrMoV steel (WWER-440) and 9% Cr based ferritic-martensitic steels (...
One of the options to mitigate the effects of irradiation on reactor pressure vessels is to thermall...
Surveillance specimens of 15Kh2MFA reactor pressure vessel (RPV) steel and Sv-10KhMFT weld metal wer...
One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to th...
Surveillance specimens of 15Kh2MFA reactor pressure vessel (RPV) steel and Sv-10KhMFT weld metal wer...
The analysis of WWER-440 RPV welds mechanical properties and behaviour of nanoscale structural featu...
It is believed that in the next decade or so, several nuclear reactor pressure vessels (RPVs) may ex...
The results of long term research programme concerning the determination of irradiation embrittlemen...
Re-irradiation data available in RRC-KI and in Fortum Engineering /VTT is analysed in order to ident...