1-18
Reactor systems developed by OKBM in the development of the atomic energy industry, nuclear power, and the nuclear-powered fleet in Russia
V. I. Kostin, F. M. Mitenkov, V. V. Petrunin, I. V. Serov and Yu. K. Panov, et al.
19-24
Problems of BN-800 construction and the possibilities of developing advanced fast reactors
V. I. Kostin and B. A. Vasil’ev
25-30
Reactor systems in nuclear-powered ships — present status, service life extension, and prospects
V. I. Kostin, Yu. K. Panov, V. I. Polunichev and O. A. Yakovlev
31-35
Floating power-generating unit with a KLT-40S reactor system for desalinating sea water
V. I. Kostin, Yu. K. Panov, V. I. Polunichev and I. E. Shamanin
36-41
VBÉR-300 reactor system and power-generating units for regional nuclear power production
V. I. Kostin, V. V. Petrunin, O. B. Samoilov and A. V. Kurachenkov
42-47
Economic effect of the development and operation of serially produced propulsion nuclear power systems
F. M. Mitenkov, B. A. Averbakh and I. N. Antyufeeva
48-53
VVÉR-1000 TVSA fuel assembly: Direction of development and operating results
V. B. Kaidalov, D. G. Preobrazhenskii, A. I. Romanov, O. B. Samoilov and A. A. Fal’kov, et al.
54-59
Development and investigation of the regulator of the passive heat-removal system for the Kudankulam nuclear power plant (India)
V. I. Polunichev, G. P. Shumailov, P. A. Gorbunov, M. M. Grigor’ev and A. A. Plakseev, et al.
60-66
Analysis of emergency regimes of modular HTGR
N. G. Kodochigov and S. F. Shepelev
67-74
Development of a design for the GT-MHR energy conversion unit
V. I. Kostin, N. G. Kodochigov, S. E. Belov, A. V. Vasyaev and V. F. Golovko, et al.
75-81
Computational and experimental investigations of the neutron-physical characteristics of the GT-MHR core
N. G. Kodochigov, Yu. P. Sukharev, E. V. Marova, V. F. Boyarinov and V. I. Bryzgalov, et al.
82-85
Possibility of operating GT-MHR with different fuels
N. G. Kodochigov, Yu. P. Sukharev, E. V. Marova and S. G. Usynina