Russian Federation
State of HTGR development in Russia
Golovko, V.F.; Kiryushin, A.I.; Kodochigov, N.G.; Kuzavkov, N.G. (OKB Mechanical
Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--899, pp:31-46
The essential trends of HGR development in the Russian Federation
Sukharev, Yu.P. (OKB Mechnical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--988, pp:33-45
Radiation damage and life-time evaluation of RBMK graphite stack
Platonov, P.A.; Chugunov, O.K.; Manevsky, V.N.; Karpukhin, V.I. (Russian Research
Centre Kurchatov Inst., Moscow (Russian Federation). Reactor Material Div.)
IAEA-TECDOC--901, pp:79-90
Assessments of the stresses and deformations in an RBMK graphite moderator brick
Jones, C.J.; Davies, M.A.; Marsden, B.J. (AEA Technology, Risley (United Kingdom));
Bougaenko, S.E.; Baldin, V.D.; Demintievski, V.N.; Rodtchenkov, B.S.; Sinitsyn, E.N. (Research and Development Inst. of Power Engineering (RDIPE), Moscow (Russian Federation))
IAEA-TECDOC--901, pp:137-149
The state of the graphite stack at Leningrad NPP, unit 2, after 16.5 years of operation
Baldin, V.D.; Rodtchenkov, B.S. (Research and
Development Inst. of Power Engineering (RDIPE),
Moscow (Russian Federation)); Platonov, P.A.;
Chugunov, O.K. (Russian Research Centre,
Kurchatov Inst. Moscow (Russian Federation))
IAEA-TECDOC--901, pp:161-165
GT-MHR spent fuel storage disposal without processing
Kiryushin, A.I.; Kuzavkov, N.G.; Gushin,
Yu.L.; Sukharev, Yu.P. (OKBM, Nizhny
Novgorod (Russian Federation)); Chudin,
A.G. (Minatom, Moscow (Russian Federation)); Richards, M.; Shenoy, A.
(General Atomics, San diego, CA (United States))
IAEA-TECDOC--1043, pp:191-199
Radiation behaviour of graphite for HTGR
Shtrombakh, Ya.I.; Platonov, P.A.; Gurovich,
B.A.; Alekseev, V.M. (Russian Research Centre
Kurchatov Inst., Moscow (Russian Federation))
IAEA-TECDOC--901, pp:251-262
Russian graphite nuclear application. History, state of the art, future
Platonov, P.; Shtrombakh, Ya.; Chugunov, O.; Kaprukhin, V.; Manevski, V.; Alexeev, V.
(Russian Research Centre Kurchatov Inst., Moscow (Russian Federation))
IAEA-TECDOC--1043, pp:269-274
The GTHMR Project
A. Kiryushin, N. G. Kodochigov, OKB Mechanical Engineering, Russia
HTR-2002, pp:1-5
Investigation of Criticality Parameters of High Temperature Reactors at the Kurchatov Institute’s ASTRA Critical Facility
N. E. Kukharkin, E. S. Glushkov, G. V. Kompaniets, V. A. Lobyntsev, D. N. Polyakov, O. N. Smirnov, Institute of Nuclear Reactors, RRC Kurchatov Institute, Russia
HTR-2002, pp:1-5
The Behaviour of Fission Products in the HTGR Fuel Irradiated in the IVV-2M Reactor
K. N. Koscheyev, Sverdlovsk Branch of R&D Institute of Power Engineering, Zarechny and A. S. Chernikov, RPA Lutch, Russia
HTR-2002, pp:1-5
Mathematical Model and Computer Code for Coated Particles Performance at normal operating conditions
I. Golubev, I. Kadarmetov, V. Makarov, All-Russian Research Institute of Inorganic Materials (VNIINM), Moscow
HTR-2002, pp:1-16
The Behavior of HTR-10 Fuel Under Irradiation
Tang Chunhe, Fu Xiaoming, Zhu Junguo, Institute of Nuclear Energy Technology, Beijing, CHINA; Konstantin N. Koshceev, Alexandre V. Kozlov, Institute of Nuclear Materials, Zarechny, RUSSIA; Oleg G. Karlov; Yu.G. Degaltsev, Vladimir I. Vasiliev, Russian Research Center “Kurchatov Institute” Moscow, RUSSIA
HTR-2004, pp:1-17
Program of GT-MHR Fuel Development and Justification
N. Kodochigov, Yu. Sukharev, OKBM, RUSSIA; N. Ponomarev-Stepnoy, Yu. Degaltsev, RCC KI, RUSSIA; V. Novikov, I. Kadarmetov, V. Makarov, VNIINM, RUSSIA; V. Sulaberidze NIIAR, RUSSIA; A. Chernikov, SPA Lutch, RUSSIA; D. Mc Eachern, R. Noren, GA, USA
HTR-2004, pp:1-9
GTMHR Code
V.A. Bolnov, V.S. Vostokov, V.S. Gorbunov, V.V. Shashkov, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-15
Provision of the Possibility to Increase Helium Temperature at the core Outlet of GT-MHR-Type Reactor to the Level of 1000 centigrade
V.N. Afanasev, N.G. Kodochigov, N.G. Kuzavkov, S.F. Shepelev, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-7
Development and Calculation of Neutronic Benchmark Models For The GT-MHR Type Reactor Cells
V. Boyarinov, E. Glushkov, V. Davidenko, P. Fomichenko, V. Tsibulsky, RRC Kurchatov Institute, Moscow, RUSSIA; E. Marova, Yu. Sukharev, OKBM, Nizhny Novgorod, RUSSIA; E. Mitenkova, N. Novikov, IBRAE, Moscow, RUSSIA
HTR-2004, pp:1-18
Calculation-Information Code "GT-MHR Analyzer"
N.G. Kodochigov, A.V. Vasyaev, V.V, Bankrutenko, V.F. Golovko, L.E. Kuznetsov, I.V. Dmitrieva, E.A. Zvyagin, M.E. Ganin, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-7
Influence Of Htgr Parameters On The Configuration And Characteristics Of Power Conversion Unit With Direct Gas-Turbine Cycle
N.G. Kodochigov, A.V. Vasyaev, V.F. Golovko, N.G. Kuzavkov, I.V. Dmitrieva, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-6
Power Conversion Unit With Direct Gas-Turbine Cycle For Electric Power Generation As A Part Of GT-MHR Reactor Plant
V.I. Kostin, N.G. Kodochigov, A.V. Vasyaev, V.F. Golovko, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-12
Investigation of Full Electromagnetic Suspension For Turbomachine Rotor
V.I. Kostin, N.G. Kodochigov, V.V. Drumov, V.S. Vostokov, I.V. Drumov, S.E. Belov, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-18
Investigation of Influence of Integral Component In Proportional Integral Differential Regulator Of Electromagnetic Bearing Control System On Stability and Dynamics Of GT-MHR Turbomachine
F.M. Mitenkov, V.S. Vostokov, V.S. Gorbunov, V.V. Drumov, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-7
Rotation Investigations Of Rotor On Electromagnetic Suspension. Calculation And Methods
F.M. Mitenkov, N.G. Kodochigov, V.S. Vostokov, V.S. Gorbunov, V.V. Drumov, E.F. Sabaev, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-8
Comparison of Horizontal and Vertical Layout of The Rotor on Electromagnetic Suspension
V.S. Vostokov, N.G. Kodochigov V.S. Gorbunov, A.V. Khodykin, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-7
Design And Analysis Under Conditions Of Limited Space By 3D Means
M.K. Vladimirsky, A.V. Vasyaev, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-5
Control System of NPP with GT-MHR Power Unit
A.V. Vasyaev, V.F. Golovko, A.B. Pobedonostsev, V.S. Gorbunov, V.V. Drumov, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-9
Simulator Development For GT-MHR Reactor Plant Designing
V.A. Bolnov, E.V. Bogdanova, V.S. Vostokov, V.S. Gorbunov, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-8
Development Of Shaft Gas Seal
V.M. Rogozhin, V.B. Zinoviev, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-5
Materials Used For The Main Elements of Hightemperature Elements Of HTGR Turbocompressor
N.G. Kodochigov, A.A. Romantsov, S.A. Dolgov, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-13
Vertical Turbogenerator With Helium Cooling
Ya.B. Danilevich, E.Yu. Anishev, N.S. Delfontsev, V.I. Kostin
HTR-2004, pp:1-7
Results of Experimental Investigations on Sliding Seal Mock-up for GT-MHR RP Turbomachine
N.G. Kodichigov, S.E. Belov, V.I. Fomichev, A.I. Maxyanin, I.B. Orlov, M.N. Borokov, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-4
Experimental Investigation For The Optimization Of Powerful Turbine Plants Gas Coolers Heat Exchange Surface Ribbing
O.A. Bikh, B.M. Kamashev, N.G. Kodochigov, A.E. Komarov, A.E. Krasilschikov, N.G. Kusavkov, A.V. Malkov, V.M. Rulev, V.A. Sobolev, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-4
Experimental Investigation Of High-Temperature High-Performance Recuperator
O.A. Bikh, V.M. Golovko, I.V. Dmitrieva, B.M. Kamashev, A.E. Krasilschikov, A.V. Malkov, V.M. Rulev, OKBM, Nizhny Novgorod, RUSSIA
HTR-2004, pp:1-6
Design And Experiment Investigations of Compact Recuperators For Reactor Plants With Gas-Turbine Cycle
O.A. Bikh, V.F. Golovko, I.V. Dmitrieva, N.G. Kuzakov, L.K. Nikanorov
HTR-2004, pp:1-6
Analysis and choice of characteristics of the HTGR spherical fuel elements
Grebennik, V.N.; Degal'tsev, Yu.G.; Karpov, A.V.;
Ponomarev-Stepnoy, N.N.; Protsenko, A.N.; Tikhonov, N.I.;
Khrulev, A.A
IWGGCR--8, pp:5-18
Gas-cooled breeders as an alternative to LMFBR's. Hard and soft neutron spectra.
Fejnberg, S.M. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IAEA-TECDOC--154, pp:21-61
GT-MHR as economical highly efficient inherently safe modular gas cooled reactor for electric power generation
A.G.Baydakov, N.G.Kodochigov, N.G.Kuzavkov, V.E.Vorontsov (OKBM, Nizhny Novgorod, Russia)
IAEA-TECDOC--1210, pp:23-34
Review of current work on investigation of HTGR fuel in the
Union of Soviet Socialist Republics
Grebennik, V.N. (Gosudarstvennyj Komitet po Ispol'zovaniyu
Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj
Ehnergii)
IWGGCR--25, pp:25-27
Fuel element for the gas-cooled fast breeder reactor BGR-300
Kolganov, V.D.; Kruglov, A.L.; Ulasevich, V.K.; Knyazev,
V.A.; Tikhovov, N.I.; Ponomarev-Stepnoy, N.N.; Ashihmin,
V.P.; Vorobjev, M.A
IWGGCR--8, pp:40-50
Project of demonstration nuclear heating plant using pool-type water reactor
Baranaev, Yu.D.; Osennikh, G.M.; Sergeev, Yu.A. (State Research Center of Russian
Institute of Physics and Power Engineering (SRC RF-IPPE), Obninsk (Russian Federation)); Mikhan, V.I.; Romenkov, A.A. (Research and Development Institute of Power Engineering (RDIPE), Moscow (Russian Federation))
IAEA-TECDOC--1056, pp:45-54
Creation of nuclear heating plants in Russia: present status and prospects for the future
Gureeva, L.V.; Kurachenkov, A.V. (OKB Mechanical Engineering, N. Novgorod (Russian Federation))
IAEA-TECDOC--1056, pp:55-60
Calculation studies of behaviour of HTGR spherical fuel elements during an acident induced by a high-positive reactivity fast introduction
A.O. Gol'tsev
IAEA-TC--389.26, pp:56-82
Problems of creating fuel elements for fast gas-cooled reactors working on N2O4-dissociating coolant
Nesterenko, V.B.; Zelensky, V.F.; Kolykhan, L.I.; Karpenko,
G.V.; Krasnorutsky, V.S.; Isakov, V.P.; Ashikhmin, V.P.;
Permyakov, L.N
IWGGCR--8, pp:56-65
Investigation of air ingress accidents under depressurization of the VGM modular reactor primary circuit
Kuzavkov, N.G.; Tonny, S.I.; Shepelev, S.F. (OKBM, Nizhny Novgorod (Russian Federation)); Klyukin, S.M. (Minatom RF, Moscow (Russian Federation)); Zyryanov, S.I. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Inst. Atomnoj Ehnergii)
IAEA-TECDOC--784, pp:61-66
Nuclear power plant with pressure vessel boiling water reactor VK-300 for district heating and electricity
supply
Kuznetsov, Yu.N.; Lisitsa, F.D.; Tokarev, Yu.I.; Romenkov, A.A. (Research and
Development Institute of Power Engineering, Moscow (Russian Federation))
IAEA-TECDOC--1056, pp:61-64
Problems of heat sources modeling on stage of isolated power systems expansion planning
Malenkov, A.V.; Reshetnikova, L.N.; Sergeev, Yu.A. (State Scientific Center of the
'Institute of Physics and Power Engineering', Obninsk (Russian Federation))
IAEA-TECDOC--1056, pp:65-73
The calculation - experimental investigations of the HTGR fuel element construction
Eremeev, V.S.; Kolesov, V.S.; Chernikov, A.S
IWGGCR--8, pp:66-78
Features of Adapting Gas Turbine Cycle and Heat Exchangers for HTGRs
V.F. Golovko, I.V. Dmitrieva, N.G.Kodochigov, N.G.Kuzavkov
OKB Mechanical Engineering, Nizhny Novgorod, CHUDIN A.G., Ministry of the Russian Federation for Atomic Energy, Moscow
IAEA-TECDOC--1238, pp:67-77
Behaviour of HTGR coated particles and fuel elements under
normal and accident conditions.
Deryugin, A.I.; Koshcheev, K.N.; Momot, G.V.; Khrulyov,
A.A.; Chernikov, A.S. (Scientific and Industrial Association
''Lutch'', Podol'sk (USSR))
IWGGCR--25, pp:71-77
Flow schemes and design features of HTGR residual heat removal systems
Golovko, V.F.; Kiryuschin, A.I.; Kuzavkov, N.G. (OKBM, Nizhny Novgorod
(Russian Federation))
IAEA-TECDOC--757, pp:72-75
Effects of the fuel elements pebble bed structural non-uniformity
on the HTGR physical and thermophysical characteristics.
Yevsevev, V.I.; Kiryushin, A.I.; Kuzavkov, N.G.; Mordvintsev,
V.M.; Sukharev, Yu.P (Experimenta Machine Building Design Bureau, Gorki (Union of Soviet Socialist Republics))
IWGGCR--24, pp:72-77
In-pile tests of HTGR fuel particles and fuel elements
Chernikov, A.S.; Kolesov, V.S.; Deryugin, A.I.
(I.V. Kurchatov Institute of Atomic Energy,
Moscow (Russian Federation))
IWGGCR--13, pp:74-80
The Apatity nuclear heating plant project: modern technical and economic issues of nuclear heat
application in Russia
Adamov, E.O.; Romenkov, A.A. (Research and Development Institute of Power
Engineering (RDIPE), Moscow (Russian Federation))
IAEA-TECDOC--1056, pp:75-83
Systems for heat transport from an HTGR to industrial processes
Golovko, V.F.; Kiryushin, A.I.; Kuzavkov, N.G. (OKBM, Nizhnij Novgorod (Russian Federation))
IAEA-TECDOC--761, pp:76-79
Gas-cooled fast reactors with dissociating gases
Krasin, A.K. (AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki)
IAEA-TECDOC--154, pp:88-100
Nuclear floating power desalination complexes
Panov, Y.K.; Polunichev, V.I. (OKB Mechanical Engineering, Nizhny Novgorod (Russian
Federation)); Zverev, K.V. (Ministry of Russian Federation for Atomic Energy, Moscow (Russian Federation))
IAEA-TECDOC--1056, pp:93-104
Small demonstration HTGR concept
Kiryushin, A.I. (Gor'kovskij Politekhnicheskij Inst., Gorki
(USSR))
IWGGCR--19, pp:96-103
Physical and technical characteristics of dissociating N2O4 as a coolant for fast power reactors
Nesterenko, V.B. (AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki)
IAEA-TECDOC--154, pp:101-124
HTGR spherical fuel elements of the monolithic type bound by pyrocarbon
Zelenskiy, V.F.; Gurin, V.A.; Keruchen'ko, S.S.; Konotop,
Yu.F
IWGGCR--8, pp:106-112
Assessing seismic effects in gas cooled reactor building and
pipeline design.
Chikunova, T.N. (All-Union Project and Research Inst. of
Complex Power Technology, Leningrad (USSR))
IWGGCR--22, pp:111-113
Uncertainties in the analysis of water ingress accident for the
HTGR cores.
Gorbunov, V.S.; Golovko, V.F.; Glushkov, E.S.
(Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii
SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii); Kiryushin,
A.I.; Kuzavkov, N.G.; Sukharev, Yu.P. (Experimental Machine
Building Design Bureau, Gorki (USSR))
IWGGCR--24, pp:112-116
Seismic stability of VGM type high temperature gas cooled
reactors.
Zhukov, V.V.; Kaidalov, V.B.; Kiryushin, A.I.; Silaev, V.M.
(Experimental Machine Building Design Bureau, Gorki (USSR))
IWGGCR--22, pp:113-121
HTGR spherical fuel elements and their experimental development
Chernikov, A.S.; Koshelev, Yu.V.; Mikhailichenko, L.I.;
Kuznetzov, A.A
IWGGCR--8, pp:113-132
Analysis of afterheat removal from modular HTGRs during accidents, and a concept for use of
spherical fuel elements in LWRs
Mosevitskij, I.S.; Goltsev, A.O.; Mikhailov, P.V.; Tsibulskij, V.F.; Davidenko,
V.D.; Popov, V.S.; Udyanskij, Yu.N. (Gosudarstvennyj Komitet po
Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Inst.
Atomnoj Ehnergii)
IAEA-TECDOC--757, pp:117-122
Problems of investigation of HTGR fuel elements under
loss-of-pressure accident conditions.
Mosevitskij, I.S.; Djakov, A.V. (Gosudarstvennyj Komitet po
Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst.
Atomnoj Ehnergii)
IWGGCR--25, pp:124-131
Technical and economic evaluation of nuclear seawater desalination systems
Grechko, A.G.; Romenkov, A.A.; Shishkin, V.A. (Research and Development Institute of
Power Engineering (RDIPE), Moscow (Russian Federation))
IAEA-TECDOC--1056, pp:129-138
Main gas circulator for VG-400 reactor plant
Mitenkov, F.M.; Kostin, V.I.; Novinskij, E.G.; Kuropatov, A.I.; Protsenko, A.N.; Smirnov, V.P.; Stolyarevskij, A.Ya. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IWGGCR--17, pp:130-138
Preparation of microspherical fuel kernels for high-temperature gas-cooled reactors using the mechanical spheroidization method
Voloshchuk, A.I.; Gurin, V.A.; Odejchuk, N.P.; Chajka, S.S
IWGGCR--8, pp:133-139
Investigation of graphite column bricks of Leningrad NPP unit 3 RBMK-1000 reactor after 18 years of operation
P.A. Platonov, O.K. Chugunov, Ya.I. Shtrombakh, V.M. Alekseev, N.S. Lobanov,
V.N. Manevski, V.I Karpukhin, I.F. Novobratskaya, I.A. Frolov,
V.M. Semochkin, V.A. Denisov, A.V. Borodin, A.A. Kalinnikov,
D.E. Furkasov, Yu.V. Garusov, M.A. Pavlov, A.N. Ananiev,
A.V. Makushkin, V.N. Rogozin, V.P. Aleksandrov, V.D. Baldin
TCM-Manchester99, pp:134-142
Uncertainties in HTGR neutron-physical characteristics due to
computational errors and technological tolerances.
Glushkov, E.S.; Grebennik, V.N.; Davidenko, V.G.; Kosovskij,
V.G.; Smirnov, O.N.; Tsibul'skij, V.F. (Gosudarstvennyj
Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow
(USSR). Inst. Atomnoj Ehnergii); Sukharev, Yu.P.
(Experimental Design Bureau of Machine Building, Gorki
(USSR))
IWGGCR--24, pp:136-145
Structure-stable alloy for structural components of the high-temperature gas-cooled reactor with coolant temperature of 950 deg C
Dushin, Y.A.; Gribov, N.N.; Ignatov, V.A.; Medvedev, N.A. (Experimental and Industrial Enterprise ''Prometey'', Leningrad (USSR))
IAEA-TC--389.26, pp:138-154
Features of spherical uranium-graphite HTGR fuel elements control
Kreindlin, I.I.; Oleynikov, P.P.; Shtan, A.S
IWGGCR--8, pp:140-158
Main principles of low-power HTGR radiation safety ensurance
Bylkin, B.K.; Grebennik, V.N.; Kirjushin, A.I.; Kuzovkov, N.G.; Ponomorjev-Stepnoi, N.N.; Hruljev, A.A.; Yanushevich, I.V
IAEA-TC--389.26, pp:155-174
HTGR fuel elements operating conditions during accidents with
abrupt power raise.
Gorbunov, V.S.; Kiryushin, A.I.; Kuzavkov, N.G.; Sukharev,
Yu.P. (Experimental Machine Building Design Bureau, Gorki
(USSR))
IWGGCR--25, pp:155-157
The ANGSTREM project: present status and development activities
Stepanov, V.S.; Legyuenko, S.K. (EDB 'Gidropress', Podol'sk (Russian Federation));
Grigoriev, O.G.; Gromov, B.F.; Dedul, A.V.; Leonchyk, M.P.; Pashkin, Yu.G.;
Pankratov, D.V.; Chekunov, V.V.; Skorikov, D.E. (SSC RF IPPE, Obninsk (Russian Federation))
IAEA-TECDOC--1056, pp:157-164
Radionuclide characterization of graphite stacks from plutonium production reactors of the Siberian group of chemical enterprises
A.V. Bushuev, Yu.M. Verzilov, V.N. Zubarev, A.E. Kachanovsky, I.M. Proshin,
E.V. Petrova, T.B. Aleeva, A.A. Samarkin, B.G. Silin, A.M. Dmitriev, E.V. Zakharova,
S.I. Ushakov, I.I. Baranov, Yu.I. Kabanov, E.N. Kolobova A.G. Nikolaev
TCM-Manchester99, pp:160-175
SVBR-75: a reactor module for renewal of WWER-440 decommissioning reactors - safety and
economic aspects
Stepanov, V.S.; Kulikov, M.L.; Ilyin, O.G.; Klimov, N.N. (EDB 'Gidropress', Podol'sk
(Russian Federation)); Chekunov, V.V.; Grigoriev, O.G.; Gromov, B.F.; Leonchyk, M.P.;
Pashkin, Yu.G.; Pankratov, D.V.; Toshinsky, G.I.; Skorikov, D.E. (SSC RF IPPE, Obninsk (Russian Federation))
IAEA-TECDOC--1056, pp:165-176
Fission product diffusion in fuel element materials for HTGR
Chernikov, A.S.; Khromov, Yu.F.; Lyutikov,
R.A.; Gusev, A.A. (I.V. Kurchatov Institute of
Atomic Energy, Moscow (Russian Federation))
IWGGCR--13, pp:170-181
Main characteristics and design features of steam generators for VG-400 plant
Golovko, V.F.; Grebennik, V.N.; Gol'tsev, A.O.; Ivanov, S.M.; Sergeev, A.I.; Pospelov, V.N. (I.V. Kurchatov Institute of Atomic Energy, Moscow (Russian Federation))
IWGGCR--15, pp:175-181
Properties of lead-bismuth coolant and perspectives of non-electric applications of lead-bismuth reactor
Martynov, P.N.; Ivanov, K.D. (State Scientific Center of R.F., Institute for Physics and
Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1056, pp:177-184
Corrosion tests of matrix graphites
Vavilin, A.I.; Kulikov, E.T.; Mozzherin, S.I.; Chernikov, A.S. (Scientific and Industrial
Association 'Lutch', Podol'sk (Russian Federation))
IAEA-TECDOC--690, pp:183-192
Development of small (10 MW thermal) nuclear plant with lead-bismuth coolant for electricity and heat
co-generation, production of fresh water and hydrogen
Komkova, O.I.; Kononenko, G.J.; Puchkov, P.V.; Sidorov, V.I.; Trevgoda, M.M.
(Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation));
Verhovodko, S.Z. (St. Petersburg Marine Building Bureau, St. Petersburg (Russian Federation))
IAEA-TECDOC--1056, pp:185-188
Non-electric applications of pool-type nuclear reactors
Adamov, E.O.; Cherkashov, Yu.M.; Romenkov, A.A. (Research and
Development Inst. of Power Engineering, Moscow (Russian Federation))
IAEA-TECDOC--923, pp:187-195
Physics and engineering of plants with large gas-cooled fast breeder reactors
Ponomarev-Stepnoj, N.N.; Glushkov, E.S.; Grebennik, V.N.; Demin, V.E.; Khrulev, A.A
IAEA-TECDOC--154, pp:189-232
Radiation effect on the graphite of HTGR
Platonov, P.A.; Strombach, Ya.I.; Karpukhin, V.I.; Gurovich, B.A.; Chugunov, O.K.; Trofimchuk, E.I. (Gosudarstvennyj Komitet po
Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IWGGCR--11, pp:201-206
Specific behavior of reflector and matrix graphite under high temperature irradiation
Platonov, P.A.; Karpukhin, V.I.; Shtrombakh, Ya.I.; Alekseev, V.M.; Chugunov, O.K.;
Gurovich, B.A.; Trofimchuk, E.I. (I.V. Kurchatov Inst. of Atomic Energy, Moscow (Russian Federation). Dept. of Research Reactors and Technology)
IAEA-TECDOC--690, pp:205-209
Promising materials for HTGR high temperature heat exchangers
Kuznetsov, E.V.; Tokareva, T.B.; Ryabchenkov, A.V.; Novichkova, O.V.;
Starostin, Yu.D. (Tsentral'nyj Nauchno-Issledovatel'skij Inst. Tekhnologii
Mashinostroeniya, Moscow (USSR))
IWGGCR--18, pp:205-206
Matrix graphite for HTGR spherical fuel elements some their properties
Chernikov, A.S.; Mozzherin, S.I.; Reshetnikov, V.A. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow.
Inst. Atomnoj Ehnergii)
IWGGCR--11, pp:207-212
Utilization of HTGR heat and its transfer to industrial facilities
Golovko, V.F.; Guchshin, U.L.; Kodochigov, N.G.; Kuzavkov, N.G. (OKB Mechanical
Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1056, pp:209-216
Experimental investigations of heat exchange and hydrodynamics on models of a VG-400 steam generator tube bundle made up of small diameter helicoils
Golovko, V.F; Ivaskov, N.A.; Obukhov, P.I.; Pospelov, V.N.; Sergeev, A.I. (I.V. Kurchatov Institute of Atomic Energy, Moscow (Russian Federation))
IWGGCR--15, pp:210-214
High temperature technological heat exchangers and steam generators with helical coil assembly tube bundle
Korotaev, O.J.; Mizonov, N.V.; Nikolaevsky, V.B.; Nazarov, E.K
IAEA-TC--389.26, pp:212-251
Micro fuel elements and fuel elements studies with the use of pre-irradiation
Ponomarev-Stepnoy, N.N.; Khroulev, A.A.; Momot, G.V.;
Solenkov, V.F.; Koshelev, Yu.V.; Gurin, V.A
IWGGCR--8, pp:212-225
Analysis of some accident conditions in confirmation of the HTGR safety
Grebennik, V.N.; Grishanin, E.I.; Kukharkin, N.E.; Mikhailov, P.V.; Pinchuk, V.V.; Ponomarev-Stepnoy, N.N.; Fedin, G.I.; Shilov, V.N.; Yanushevich, I.V. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IWGGCR--1, pp:214-221
Power technology complex for production of motor fuel from brown coals with power supply from NPPs
Troyanov, M.F.; Poplavskij, V.M.; Sidorov, G.I.; Bondarenko, A.V.; Chebeskov, A.N.;
Chushkin, V.N.; Karabash, A.A. (State Research Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk (Russian Federation)); Krichko, A.A.; Maloletnev, A.S. (Combustible Resources Institute, Moscow (Russian Federation))
IAEA-TECDOC--1056, pp:217-225
Use of natural circulation mechanism core cooling of high temperature helium-cooled reactors as a means of safety enhancement
Belyakov, M.S.; Kolganov, V.D.; Kochetkov, S.S.; Smetannikov, V.P.; Ulasevich, V.K. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IWGGCR--1, pp:222-233
Strength analysis code for graphite structural components in uranium-graphite nuclear reactors
Rodchenkov, B.S.; Platonov, P.A.; Manevskij, V.N.; Kashirin, B.A.; Chugunov, O.K.
(Research and Development Inst. of Power Engineering (Russian Federation))
IAEA-TECDOC--690, pp:225-230
Reactor tests of spherical fuel elements and HTGR microfuel elements and study of their state after irradiation
Gurin, V.A.; Degaltsev, Yu.G.; Ponomarev-Stepnoy, N.N.;
Tikhonov, N.I.; Utkin, Yu.M.; Khrulev, A.A.; Chernikov,
A.S.; Shtrombakh, Ya.I
IWGGCR--8, pp:226-243
Coupling of AST-500 heating reactors with desalination facilities
Kourachenkov, A.V. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1056, pp:229-234
Equipment and materials for coupling interfaces of a nuclear reactor with desalination and heating plants
based on floating NHPS
Panov, Yu.K.; Polunichev, V.I. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1056, pp:249-262
The choice of equipment mix and parameters for HTGR-based nuclear cogeneration plants
Malevski, A.L.; Stoliarevski, A.Ya.; Vladimirov, V.T.; Larin, E.A.; Lesnykh, V.V.; Naumov, Yu.V.; Fedotov, I.L
IAEA-TC--389.26, pp:252-270
Prospects for application of high-temperature helium reactor (HTHR) to provide for power needs in refineries and petrochemical plants
Feigin, E.A.; Raud, E.A.; Romanova, E.G.; Panasenko, P.A.; Nikitin, V.N
IAEA-TC--389.26, pp:271-288
Use of reactor plants of enhanced safety for sea water desalination, industrial and district heating
Panov, Yu.; Polunichev, V. (OKB Mechanical Engineering, Nizhny Novgorod
(Russian Federation)); Zverev, K. (Ministry for Atomic Energy, Moscow
(Russian Federation))
IAEA-TECDOC--923, pp:281-293
Nuclear source of district heating in the north-east region of Russia
Dolgov, V.V. (State Scientific Center of the Russian Federation, Institute of Physics and
Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1056, pp:281-290
Safety questions for a plant with a dissociating gas as a coolant
Sharovarov, G.A. (AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki)
IAEA-TECDOC--154, pp:286-303
Neutron-physical aspects of the HTR concept with spherical fuel elements
Ponomarev-Stepnoy, N.N.; Grebennik, V.N.; Glushkov, E.S.; Kucharkin, N.E
IAEA-TC--389.26, pp:289-314
Nuclear heat applications in Russia: Experience, status and prospects
Mitenkov, F.M.; Kusmartsev, E.V. (OKB Mechanical Engineering, Nizhny Novgorod
(Russian Federation))
IAEA-TECDOC--1056, pp:291-312
Safety of gas-cooled fast reactors
Kovalevich, O.M. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IAEA-TECDOC--154, pp:304-321
Improved safety nuclear power - and - heating plant with HTGR of modular type
Bogoyavlenskii, R.G.; Vinogradov, V.P.; Glebov, V.P.; Grebennik, V.N.; Ponomarev-Stepnoi, N.N.; Hruljov, A.A
IAEA-TC--389.26, pp:315-327
Coolant technology and corrosion stability of construction materials in N2O4
Sukhotin, A.M.; Lantratova, N.Ya.; Trubnikov, V.P.; Atroshenko, Eh.I. (Gosudarstvennyj Inst. Prikladnoj Khimii, Moscow (USSR); AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki)
IAEA-TECDOC--154, pp:322-363
The investigation of HTGR fuel regeneration process
Lazarev, L.N.; Bertina, L.E.; Popik, V.P.; Isakov, V.P.;
Alkhimov, N.B.; Pokhitonov, Yu.A
IWGGCR--8, pp:369-382
On applicability of gas-fluoride technology to regeneration of spent HTGR fuel elements
Prusakov, V.N.; Trotsenko, N.M
IWGGCR--8, pp:383-387
Problems of attracting nuclear energy resources in order to provide economical and rational consumption of fossil fuels
Nazarov, E.K.; Nikitin, A.T.; Ponomarev-Stepnoy, N.N.; Protsenko, A.N.; Stolyarevskii, A.Ya.; Doroshenko, N.A. (State Institute of Nitrogen Industry, Moscow (USSR); I.V. Kurchatov Institute of Atomic Energy, Moscow (USSR))
IAEA-TC--389.26, pp:466-486
Substantiation of choice of the main physical and thermohydraulic parameters of reactor plant with small power HTGR
Afanasyev, V.N.; Golovko, V.F.; Zhigulsky, V.N.; Karpov, V.A.; Kiryushin, A.I.; Kuzavkov, N.G.; Sukharev, Yu.N
IAEA-TC--389.26, pp:498-520
Radiation resistance of pyrocarbon-boned fuel and absorbing elements for HTGR
Gurin, V.A.; Konotop, Yu.F.; Odejchuk, N.P.; Shirochenkov, S.D.; Yakovlev, V.K. (Kharkov Institute of Physics and Technology, Ukrainian SSR, Academy of Sciences, Kharkov (USSR)); Aksenov, N.A.; Kuprienko, V.A.; Lebedev, I.G.; Samsonov, B.V. (V.I. Lenin Nuclear Reactor Research Institute, Dimitrovgrad (USSR))
IAEA-TC--389.26, pp:521-538
Behaviour of HTGR coated fuel particles at high-temperature tests
Chernikov, A.S.; Lyutikov, R.A.; Kurbakov, S.D.; Repnikov, V.M.; Khromonozhkin, V.V.; Soloviyov, G.I
IAEA-TC--389.26, pp:562-594
Reactor tests and post-reactor examination of HTGR fuel elements and coated particles
Degaltsev, Yu.G.; Khrulev, A.A.; Mosevitskii, I.S.; Ponomarev-Stepnoi, N.N.; Tikhonov, N.I.; Yakovlev, V.V. (I.V. Kurchatov Institute of Atomic Energy, Moscow (USSR))
IAEA-TC--389.26, pp:693-710
Structural graphite for high-temperature gas-cooled reactors
Virgiliev, Yu.S.; Avramenko, P.Ya.; Grebennik, V.N.; Kalyagina, I.P.; Lebedev, I.G.; Filimonov, V.A.; Shurshakova, T.N
IAEA-TC--389.26, pp:711-724
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