V. G. Kritskii

发表

The concept for organizing automatic chemical control of the primary coolant circuit of a new-generation nuclear power station with a VVER-640 reactor

V. A. Semenov, M. R. Bagerman, N. Ya. Vilkov, 1995 .

Using experience in the decontamination of power units at nuclear power stations with RBMK reactors when decommissioning them

B. K. Bylkin, Yu. A. Zverkov, V. G. Kritskii, 1999 .

Specifics of the corrosion behavior of the alloy Zr + 1%Nb in the coolant at a nuclear power station with RBMK-1000 reactors

V. G. Kritskii, P. S. Styazhkin, I. G. Berezina, 1998 .

Developing an information-analytical system for displaying and processing chemical Monitoring data for the Leningrad NPS

V. G. Kritskii, M. N. Shvedova, V. B. Benediktov, 2001 .

Effect of the quality of the coolant on the operating reliability of items of equipment at nuclear power stations with RBMK-1000 reactors

S. P. Ivanov, V. P. Martynov, V. G. Kritskii, 2000 .

The capacities of a corrosion-fatigue monitoring system in managing the service life of steam generators operating at nuclear power stations equipped with a VVER-1000M reactor

O. P. Arkhipov, S. I. Brykov, G. F. Banyuk, 2007 .

Analysis of maintaining the water chemistry regimes at nuclear power stations equipped with RBMK-1000 reactors and the main lines of their improvement

V. F. Tyapkov, V. G. Kritskii, V. M. Tishkov, 2005 .

Corrosion of copper-alloy tubes in cooling systems of nuclear power stations

V. G. Kritskii, P. S. Styazhkin, 1997 .

Solubility of magnetite in hot nuclear power station water under reducing conditions

V. I. Zarembo, A. A. Slobodov, V. G. Kritskii, 1988 .

Solubility of magnetite in the coolant of an atomic power station equipped with a boiling-water reactor

V. I. Zarembo, A. A. Slobodov, V. G. Kritskii, 1988 .