Thermal-hydraulics, physical chemistry, and technology at nuclear power stations equipped with fast-neutron sodium-cooled reactors V. V. AlekseevA. D. EfanovA. P. Sorokin OriginalPaper Pages: 933 - 941
The results of the development of technology for using sodium as coolant for fast-neutron reactors F. A. KozlovV. V. AlekseevA. N. Volov OriginalPaper Pages: 942 - 954
Simulating the retention of molten fuel in a fast-neutron reactor during a severe accident M. V. KashcheevI. A. Kuznetsov OriginalPaper Pages: 955 - 961
Thermohydraulic studies of safety of NPPs with fast reactors A. P. Sorokin OriginalPaper Pages: 962 - 970
Thermal and chemical tests of the steam generator of unit 3 at the Kalinin nuclear power station N. N. DavidenkoN. B. TrunovS. V. Shchelik OriginalPaper Pages: 971 - 980
Development of software tools for calculating corrosion-erosion wear of pipelines at nuclear power stations V. I. BaranenkoA. V. KumovA. S. Prokopenko OriginalPaper Pages: 981 - 988
Formation of corrosion products in the coolant and deposits in the multiple forced circulation circuit of a nuclear power station equipped with an RBMK-1000 reactor V. F. TyapkovL. P. Kham’yanovV. M. Tishkov OriginalPaper Pages: 989 - 993
The effect of deposits on the tubes of a horizontal steam generator on its thermal-hydraulic characteristics Yu. S. Yur’evA. A. Luk’yanovV. B. Smykov OriginalPaper Pages: 994 - 999
Gas-turbine units for cogeneration V. I. Dlugosel’skiiV. E. BelyaevV. P. Rybakov OriginalPaper Pages: 1000 - 1003
Measurement instruments for automatically monitoring the water chemistry of reactor coolant at nuclear power stations equipped with VVER reactors. Selection of measurement instruments and experience gained from their operation at Russian and foreign NPSs Yu. A. Ivanov OriginalPaper Pages: 1004 - 1008
