Search

Impact toughness and lateral expansion of the irradiated surveillance specimens for VVER-1000 reactor pres-sure vessel have been defined using Charpy impact test. The analysis of experimental data has revealed a linear correlation of these characteristics. It was shown that a slope of the regression line is practically unchanged due to irradiation. Using the upper shelf energy test data it was also demonstrated the lateral expansion and impact toughness decrease simultaneously under the neutron irradiation.

It is shown that systematic calculation errors of functionals of the neutron flux onto WWER 1000 reactor pressure vessel are pseudorandom. The error of the neutron flux functionals is estimated on the basis of this fact and the data obtained with the reactor LR 0 benchmark and with the results of dosimetry measurements near re-actor pressure vessels.

The results of the validation of the code package MCPV that is used in the radiation exposure determination methodology for the pressure vessels of the VVER type reactors of Ukrainian NPPs are presented. The validation is carried out on the basis of the data obtained with the reactor LR-0 benchmark and of the results of dosimetry measurements behind reactor pressure vessels. It is shown the code package MCPV can be used to simulate the neutron transport through a complicated heterogeneous environment of nuclear reactor and to obtain the calculational values of functionals of the neutron flux influencing onto its pressure vessel.

Impact toughness and lateral expansion of the irradiated surveillance specimens for VVER-1000 reactor pressure vessel have been defined using Charpy impact test. The analysis of experimental data has revealed a linear correlation of these characteristics. It was shown that a slope of the regression line is practically unchanged due to irradiation. Using the upper shelf energy test data it was also demonstrated the lateral expansion and impact toughness decrease simultaneously under the neutron irradiation. [ABSTRACT FROM AUTHOR]

It is shown that systematic calculation errors of functionals of the neutron flux onto WWER-1000 reactor pressure vessel are pseudorandom. The error of the neutron flux functionals is estimated on the basis of this fact and the data obtained with the reactor LR-0 benchmark and with the results of dosimetry measurements near reactor pressure vessels. [ABSTRACT FROM AUTHOR]