Russian Federation
Current status of studies on FR fuel and structural materials in the Russian Federation
Poplavsky, V.M.;Zabudko, L.M. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1039, pp:7-14
Review of technical approaches and solutions for LMFR control rods development
Matveev, V.I.; Ivanov, A.P.; Voznesenski, R.M.; Evdokimov, V.P. (Institute of Physics and Power Engineering (IPPE), Obnisnk (Russian Federation))
IAEA-TECDOC--884, pp:12-19
Nuclear power strategy: Requirements for technology
V.V. Orlov, V.I. Rachkov
IAEA-TECDOC--1348, pp:13-19
Methods and codes for modeling thermohydraulic of fast reactor core subassemblies under nominal and non-nominal operating conditions
Sorokin, A.P.; Efanov, A.D.; Yuriev, Yu.S.; Zhukov, A.V.; Ushakov, P.A.; Bogoslovskaya, G.P. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:15-27
LMFR design and operation experience
Mitenkov, F.M.; Kiryushin, A.L.; Kamanin, Yu.L.; Kuzavkov, N.G.; Lebedev, Yu.A. (Experimental Machine Building Design Burea (OKBM), Nizhny Novgorod (Russian Federation)); Poplavsky, V.M. (Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation)); Oshkanov, N.N. (Beloyarskaya Nuclear Power Station (Russian Federation))
IAEA-TECDOC--907, pp:17-26
Operational experience with propulsion nuclear plants
Polunichev, V. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1172, pp:18-27
Development and improvement of control rods for the BN-350 and BN-600 reactors
Efremov, A.I.; Ryakhovskikh, V.I.; Ponomarenko, V.B.; Chernyshov, V.M. (Moscow Factory Polymetals, Moscow (Russian Federation))
IAEA-TECDOC--884, pp:20-33
Nuclear power of the coming century and requirements to the nuclear technology
V.V. Orlov, V. Leonov, A.G. Sila-Novitski, V. Smirnov, V. Tsikunov, A.I. Filin
IAEA-TECDOC--1348, pp:20-29
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
Method of calculation of hot channel factors for fast reactor fuel elements
Krasnoyarov, N.V. (Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR))
IAEA-TECDOC--166, pp:26-36
BN-600 power unit 15-year operating experience
Saraev, O.M.; Oshkanov, N.N.; Vylomov, V.V. (Beloyarskaya NPP (Russian Federation))
IAEA-TECDOC--907, pp:27-31
Evolution of the technical concepts of fast reactors: The concept of BREST
V.V. Orlov
IAEA-TECDOC--1348, pp:30-35
Designing of fast reactor equipment and pipelines: Normative method for calculation of long-term
cyclic strength
Zhukov, V.; Kiryushin, A. (OKBM, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--933, pp:31-46
Experience of the BN-600 reactor control rods development
Alexandrov, Yu.K.; Vasilyev, B.A.; Iskhakov, S.A.; Mishin, O.B.; Rogov, V.A.; Shabalin, A.S. (OKBM, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--884, pp:34-46
Basic safety principles of KLT-40C reactor plants
Beliaev, V.; Polunichev, V. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1172, pp:35-45
Design features of BREST reactors and experimental work to advance the concept of BREST reactors
A.I. Filin, V.V. Orlov, V.N. Leonov, A.G. Sila-Novitski, V.S. Smirnov,
V.S. Tsikunov
IAEA-TECDOC--1348, pp:36-47
Status and possibility of fuel and structural materials experimental irradiation in BN-600 reactor.
Stages of BN-600 reactor core development
Vasiljev, B.A.;Zinovjev, A.I.;Staroverov, A.I. (Experimental Machine Building Bureau, Nizhny Novgorod (Russian Federation));Maltsev, V.V.;Ogorodov, A.N. (NPP BN-600, Zarechny (Russian Federation))
IAEA-TECDOC--1039, pp:37-45
Scientific research program on actinide transmutation by use of fast reactors
Kochetkov, L.A.; Zcykunov, A.G. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj
Ehnergii SSSR, Obninsk (Russian Federation). Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--693, pp:43-45
Status of sodium cooled fast reactor development in the Russian Federation
Buksha, Yu. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (Russian Federation). Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--791, pp:45-64
Planning of ADS related R&D in the Russian Federation
N.S. Rabotnov (State Scientific Center A. J. Leipunsky Institute of Physics and Power Engineering,
Obninsk, Kaluga Region, Russian Federation)
IAEA-TECDOC--1365, pp:45-58
Current status and plans for development of NPP with BREST reactors
A.I. Filin
IAEA-TECDOC--1348, pp:48-49
Reactor aspects of electronuclear transmutation of actinides in the heavy water high flux blankets. Analysis of problems
Gai, E.V.; Ignatyuk, A.V.; Rabotnov, N.S. (Gosudarstvennyj Komitet po Ispol'zovaniyu
Atomnoj Ehnergii SSSR, Obninsk (Russian Federation). Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--693, pp:49-55
Experimental studies of BREST-OD-300 reactor characteristics on BFS facilities
I.P. Matveenko, A.M. Tsyboulia, G.N. Manturov, M.Y. Semyonov,
V.N. Kocsheyev, V.S. Smirnov, A.V. Lopatkin, V.G. Muratov, P.N. Alexeyev
IAEA-TECDOC--1348, pp:50-63
Use of carbide-nitride fuel in the USSR. A review
Majorshin, A.A.; Zabud'ko, L.M.; Bibilashvilij, Yu.K.; Bogatyr, S.M. (Vsesoyuznyj Nauchno-Issledovatel'skij Inst. Neorganicheskikh Materialov, Moscow (USSR))
IAEA-TECDOC--466, pp:51-57
Implementation of the project for the construction and operation of a nuclear heat and power plant on the basis of a floating power unit with KLT-40C reactors
Polushkin, A.K.; Kuzin, E.A. (JSC Malaya Energetika, Moscow (Russian Federation)); Vorobiov, V.M. (JSC Atomenergo, St. Petersburg (Russian Federation)); Klykov, D.M. (JSC Iceberg, St. Petersburg (Russian Federation)); Panov, J.K. (OKBM, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1172, pp:58-70
Role of fast reactors in reduction of long lived waste
Tsikunov, A.G.; Kagramanyan, V.S.; Kochetkov, L.A.; Matveyev, V.I.
(Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (Russian
Federation). Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--693, pp:58-60
Thorium utilization in solving the nuclear power fuel problem
Slesarev, I.S.; Morozov, A.G.; Tsurikov, D.F. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)
IAEA-TECDOC--412, pp:59-66
Mononitride U-Pu mixed fuel and its electrochemical reprocessing in molten salts
B.D. Rogozkin, N.V. Stepennova, Yu.E. Fedorov, O.N. Dubrovin,
M.G. Shishkov, O.A. Alekseev, T.D. Loushnikova, S.I. Balakireva, V.V. Shentiakov
IAEA-TECDOC--1348, pp:64-76
Status of sodium cooled fast reactor development in the Russian Federation
Buksha, Yu.K.; Poplavskij, V.M. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (Russian Federation). Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--741, pp:65-81
Development of vibropac MOX fuel pins serviceable up TP superhigh burnups
Mayorshin, A.A.;Gadzhiev, G.I.;Kisly, V.A.;Skiba, O.V.;Tzykanov, V.A. (Research Institute of Atomic Reactors, Dimitrovgrad (Russian Federation))
IAEA-TECDOC--1039, pp:69-92
The use of engineering features and schematic solutions of propulsion nuclear steam supply systems for floating nuclear power plant design
Achkasov, A.N.; Grechko, G.I.; Pepa, V.N.; Shishkin, V.A. (Research and Development Institute of Power Engineering, Moscow (Russian Federation)
IAEA-TECDOC--1172, pp:71-77
Radwaste transmutation in nuclear reactors
Shmelev, A.N.; Kulikov, G.G.; Apse, V.A.; Glebov, V.B. (Moskovskij
Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)); Tsurikov, D.F.; Morozov,
A.G. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow
(Russian Federation). Inst. Atomnoj Ehnergii)
IAEA-TECDOC--693, pp:77-86
Some research and development of thorium fuel cycle in Russia
Troyanov, M.F.; Ilyunin, V.G.; Kalashnikov, A.G.; Kuzminov, B.D.; Nikolaev, M.N.; Raskach, F.P.; Smetanin, E.Ya.; Tsybulya, A.M. (State Scientific Center - Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1319, pp:77-82
The BOR-60 loop-channel design for testing the BREST reactor fuel
V.N. Efimov, I.Yu. Zhemkov, N. Kozolup, V.I. Polyakov, V.T. Stepanov,
Yu.E. Stynda, V.V. Orlov, A.I. Filin, A.G. Sila-Novitski, A.A. Pikalov
IAEA-TECDOC--1348, pp:77-96
Gas-cooled fast reactors with dissociating gases
Krasin, A.K. (AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki)
IAEA-TECDOC--154, pp:88-100
3-D thermal hydraulic analysis of transient heat removal from fast reactor core using immersion coolers
Chvetsov, I.; Volkov, A. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering,
Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:89-102
Performance of BOR-60 vibropack uranium-plutonium oxide fuel pins
Gadzhiev, G.I.; Majorshin, A.A.; Petukhov, A.A. (Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR))
IAEA-TECDOC--466, pp:92-101
Research on uranium-silicide nuclear fuel
Kolyadin, V.I.; Dubrovin, K.P.; Pavlenko, V.I.; Kruglov, A.V. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii); Medvedev, A.V.; Borisov, K.A.; Konovalov, I.I. (Vsesoyuznyj Nauchno-Issledovatel'skij Inst. Neorganicheskikh Materialov, Moscow (USSR))
IAEA-TECDOC--577, pp:93-99
Development of passive safety devices for sodium-cooled fast reactors
Bagdasarov, Yu.E.; Buksha, Yu.K.; Voznesenski, R.M.; Vyunnikov, N.V.; Kornilov, V.P.; Krayev, N.D.; Mamayev, L.I.; Portyanoy, A.G.; Sorokin, A.P. (Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation))
IAEA-TECDOC--884, pp:95-104
Lead coolant as a natural safety component
V.V. Orlov, V.N. Lenov, A.G. Sila-Novitski, V.S. Smirnov, A.I. Filin, V.S. Tsikunov
IAEA-TECDOC--1348, pp:97-101
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
Issues of lead coolant technology
Yu.I. Orlov, P.N. Martynov, V.A. Gulevsky
IAEA-TECDOC--1348, pp:102-105
Low-Rynolds number k-epsilon turbulence model for calculation of fast-reactor-channel flows
Mikhin, V.I. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk,
Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:103-109
Operating experience with Beloyarsk fast reactor BN600 NPP
Saraev, O.M. (Beloyarsk Nuclear Power Plant, Sverdlovsk Region (Russian Federation))
IAEA-TECDOC--1180, pp:103-117
Main features of the BN-800 passive shutdown rods
Alexandrov, Yu.K.; Rogov, V.A.; Shabalin, A.S. (Experimental Machine Building Bureau (OKBM), Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--884, pp:105-110
Experimental and computational study on core thermohydraulics of BREST-type
reactors (lead cooling)
A.D. Efanov, A.V. Zhukov, Ju.A. Kuzina, A.P. Sorokin, V.P. Smirnov,
A.G. Sila-Novitski
IAEA-TECDOC--1348, pp:106-121
In-pile tests and post-reactor investigations of fuel pins with U-Pu Fuel
Moseev, L.I.;Vorobyev, A.N.;Zabudko, L.M.;Kiryanov, B.S.;Porollo, S.I.;Shulepin, S.V. (State Scientific Center, Institute of Physics and Power Engineering, Obninsk (Russian Federation));Antipov, S.A.;Menshikova, T.S. (Institute of Inorganic Materials, Moscow (Russian Federation))
IAEA-TECDOC--1039, pp:107-118
Review of fast reactor operation experience gained in the Russian Federation. Approaches to the co-ordinated research project
Poplavsky, V.M.; Ashurko, Yu.M.; Bagdassariv, Yu. E. (State Scientific Center of the Russian Federation (SSC RF) - Institute for Physics and Power Engineering (IPPE), Obninsk (Russian Federation)) (and others)
IAEA-TECDOC--1405, pp:107-134
Experimental investigations concerning the problem of minor actinide transmutation
Bednyakov, S.M.; Doulin, V.A.; Matveenko, I.P.; Tsibulya, A.M.; Zvonarev, A.V.
(Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (Russian
Federation). Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--693, pp:109-113
Development of thermohydraulic codes for modeling liquid metal boiling in LMR fuel subassemblies
Sorokin, G.A.; Avdeev, E.F. (Institute of Nuclear and Power Engineering, Obninsk, Kaluga Region (Russian
Federation)); Zhukov, A.V.; Bogoslovskaya, G.P.; Sorokin, A.P. (State Scientific Center of Russian Federation,
Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:110-128
A concept of specialized fast reactor for minor actinide burning
Matveyev, V.I.; Ivanov, A.P.; Efimenko, E.M. (Gosudarstvennyj Komitet po
Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (Russian Federation).
Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--693, pp:114-117
Seismic response analysis of reactor core mock-up by DINARA code
Silaev, V.M. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--829, pp:117-127
Fast reactor operating experience gained in Russia: Analysis of anomalies and abnormal operation cases
Ashurko, Y.M.; Baklushin, R.P.; Zagorulko, Y.I.; Ivanenko, V.N.; Matveyev, V.P. (State Scientific Centre of the Russian Federation, Institute of Physics and Power Engineering, Obninsk (Russian Federation)); Vasilyev, B.A. (Experimental Design Bureau of Machine Building, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1180, pp:118-145
The proposed fuel cycle of the actinide burning fast reactor DOVITA. Summary
Bychkov, A.V.; Mayorishin, A.A.; Skiba, O.V. (Nauchno-Issledovatel'skij Inst.
Atomnykh Reaktorov, Dimitrovgrad (Russian Federation))
IAEA-TECDOC--693, pp:118-118
Molten salt fuels for nuclear waste transmutation in accelerator driven systems
V.V. Ignatiev (RRC Kurchatov Institute,
Moscow, Russian Federation)
IAEA-TECDOC--1365, pp:119-129
Corrosion resistance of structure materials in lead coolant with reference to reactor
installation BREST-OD-300
A. Roussanov, V. Troyanov, G. Jachmenev, A. Demishonkov
IAEA-TECDOC--1348, pp:122-124
Thorium cycle implementation through plutonium incineration by thorium molten-salt nuclear energy synergetics
Furukawa, K. (International Thorium Molten-Salt Forum, Oiso (Japan)); Simonenko, V. (Institute of Technical Physics, Snezhinks (Russian Federation)); Mitachi, K. (Toyohashi University of Technology, Toyohashi, Aichi (Japan)); Furuhashi, A. (Nuclear Material Control Center, Tokyo (Japan)); Yoshioka, R. (Toshiba Inc., Yokohama (Japan)); Chigrinov, S. (Radiation Physics and Chemistry Problems Institute, Minsk (Belarus)); Lecocq, A. (EURIWA, Orsay (France)); Kato, Y. (Japan Atomic Energy Research Institute, Tokai (Japan))
IAEA-TECDOC--1319, pp:123-128
Analysis of emergency situations caused by BN-800 primary circuit pressure pipe depressurization
Gorbunov, V.S.; Zamiatin, V.A.; Kamanin, Yu.L.; Kuzavkov, N.G.; Sobolev, V.A. (Experimental Designing Bureau of Machine Building (OKBM), Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1406, pp:125-139
Multipurposed small fast reactor SVBR-75/100 cooled by plumbum-bismuth
A.V. Zrodnikov, V.I. Chitaykin, B.F. Gromov, O.G. Grigoriev, A.V. Dedoul,
G.I. Toshinsky, Yu.G. Dragunov, V.S. Stepanov
IAEA-TECDOC--1348, pp:125-142
Development of GRIF-SM: The code for analysis of beyond design basis accidents in sodium cooled reactors
Chvetsov, I.; Kouznetsov, I.; Volkov, A. (State Scientific Center of Russian Federation, Institute of Physics and
Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:129-149
Use of Russian technology of ship reactors with lead-bismuth coolant in nuclear power
Zrodnikov, A.V.; Chitaykin, V.I.; Gromov, B.F.; Grigoryv, O.G.; Dedoul, A.V.; Toshinsky, G.I. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)); Dragunov, Yu.G.; Stepanov, V.S. (EDO 'Gidropress', Podoolsk, Moscow (Russian Federation))
IAEA-TECDOC--1172, pp:129-157
Operation experience of the BN-600 reactor control rods
Maltsev, V.V.; Roslyakov, V.F.; Babenko, G.V.; Ogorodov, A.N. (Beloyarsk NPP BN-600 (Russian Federation))
IAEA-TECDOC--884, pp:138-149
The performance of type EP-450 ferritic-martensitic steel under neutron irradiation at low
temperatures
Khabarov, V.S.;Dvoriashin, A.M.;Porollo, S.I. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))
IAEA-TECDOC--1039, pp:139-144
Post-irradiation examination of Ti or Nb stabilized austenitic steels irradiated as BN-600 reactor fuel
pin claddings up to 87 dpa
Porollo, S.I.;Vorobyev, A.N.;Shulepin, S.V. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))
IAEA-TECDOC--1039, pp:145-151
Status of sodium cooled fast reactor development in the Russian Federation
Buksha, Yu. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1015, pp:149-178
The experience of post irradiation investigations of the BN-600 control rods
Tarasikov, V.P.; Voznesenski, R.M.; Rudenko, V.A. (Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation))
IAEA-TECDOC--884, pp:150-157
Some results on development, irradiation and post-irradiation examinations of fuels for fast reactor-actinide burner (MOX and inert matrix fuel)
Poplavsky, V.; Zabudko, L.; Moseev, L.; Rogozkin, B.; Kurina, I. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--916, pp:151-157
The use of thorium for plutonium utilization in reactors
Dekoussar, V.; Ilyunin, V.; Kalashnikov, A.; Troyanov, M. (State Scientific Centre of the Russian Federation, Leipunski Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1319, pp:154-164
Numerical analysis of the dynamic behaviour of the PEC core by the DINARA code
Silaev, V.M. (OKB Mechanical Engineering (Russian Federation))
IAEA-TECDOC--798, pp:155-163
Analysis of the preliminary results of the Russian P and T research programme
Kudryavtsev, E.G. (Ministry of the Russian Federation for Atomic Energy, Moscow
(Russian Federation))
IAEA-TECDOC--783, pp:161-163
Codes for 3-dimensional thermohydraulic calculation of fast reactor core in steady state, transient and accident conditions
Buksha, Yu.K.; Marinenko, E.E.; Touzov, A.A. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:163-174
Fuel recycling and radwaste transmutation
Murogov, V.M.; Rabotnov, N.S.; Troyanov, M.F.; Tsikunov, A.G. (Gosudarstvennyj
Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (Russian Federation).
Fiziko-Ehnergeticheskij Inst.)
IAEA-TECDOC--783, pp:165-169
Design of the advanced reactor BN-600M
Kiryushin, A.L.; Kamanin, Yu.; Kuzavkov, N.; Rogov, V. (Experimental Machine Building Design Burea (OKBM), Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--907, pp:167-175
3-D pneumatic seismic isolation of nuclear power plants
Beliaev, V.S.; Vinogradov, V.V.; Kostarev, V.V.; Kuzmitchev, V.P.; Privalov, S.A.; Siro, V.A.; Krylova, I.N.; Dolgaya, A.A.; Uzdin, A.M.; Vasiliev, A.V. (Research Center of Fundamental Engineering, CKTI-Vibroseism, St. Petersburg (Russian Federation))
IAEA-TECDOC--1288, pp:167-190
Results of the thermomechanical and fracture mechanical analysis of pipeline tee-junction break under conditions of interaction between hot sodium jet and main cold sodium flow
Birbryer, P.N.; Kiryushin, A.I.; Zhukov, V.V.; Sobolev, V.A.; Soloviev, S.A. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))
IAEA-TECDOC--1318, pp:168-185
Work on partitioning of long-lived radionuclides in the Russian Federation
Romanovskij, V.N. (Radievyj Inst., Leningrad (Russian Federation))
IAEA-TECDOC--783, pp:171-176
Use of nuclear space technology of direct energy conversion for terrestrial application
Chitaykin, V.I.; Meleta, Ye.A.; Yarygin, V.I.; Mikheyev, A.S.; Tulin, S.M. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1172, pp:178-185
Irradiation creep of austenitic steels irradiated up to high fluence in the BOR-60 reactor
Neustroev, V.S.;Shamardin, V.K. (SSC RF Research Institute of Atomic Reactors, Dimitrovgrad (Russian Federation))
IAEA-TECDOC--1039, pp:179-188
Flow resistance in rod assemblies
Korsun, A.S.; Sokolova, M.S. (Moscow Engineering Physics Institute, Institute of Physics and Power Engineering, Moscow (Russian Federation))
IAEA-TECDOC--1157, pp:184-189
Status of sodium cooled fast reactor development in the Russian Federation
Buksha, Yu. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--876, pp:186-207
Development of a neutron therapy treatment complex
Zrodnikov, A.V.; Petrov, Eh.E.; Leonov, I.N.; Ivanov, E.A.; Khoromskij, V.A. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)); Tcyb, A.F.; Mardynskij, Ju.S. (Medical Radiology Scientific Centre, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1172, pp:186-192
Computational investigation of thermohydraulic aspects of two convergent flows at different temperatures mixed in the tee junction area
Scherbakov, S.I. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1318, pp:186-205
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
Influence of high dose irradiation on structure and fracture of the C0.1-Cr16-Ni15-Mo3-Nb steel
Averin, S.A.;Kozlov, A.V.;Shcherbakov, E.N. (Research and Development Inst. of Power Engineering, Sverdlovsk Branch, Zarechny (Russian Federation))
IAEA-TECDOC--1039, pp:189-196
Models and characteristics of interchannel exchange in pin bundles cooled by liquid metal
Bogoslovskaya, G.P.; Zhukov, A.V.; Sorokin, A.P. (State Scientific Center of Russian Federation, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:190-205
Experience in development, operating and material investigation of the BOR-60 reactor control and safety rods
Ponomarneko, V.B.; Efremov, A.I.; Gadzhiev, G.I. (Moscow Factory Polymetals, Moscow (Russian Federation)); Risovany, V.D.; Zakharov, A.V.; Guseva, T.M. (Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation))
IAEA-TECDOC--884, pp:191-199
Production of gamma-sources, based on europium oxide in fast reactors
Risovany, V.D.; Zakharov, A.V.; Klochkov, E.P.; Guseva, T.M. (Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation)); Ponomarenko, V.B.; Chernyshov, V.M. (Moscow Polymetal Factory, Moscow (Russian Federation))
IAEA-TECDOC--884, pp:200-213
Advanced signal processing techniques for acoustic detection of sodium/water reaction
Yughay, V.S.;Gribok, A.V.;Volov, A.N. (Institute of Physics and Power Engineering, State Research Center, Obninsk (Russian Federation))
IAEA-TECDOC--946, pp:203-225
A problem to determine short term mechanical properties changes of ferrite-martensite and austenitic
steels as materials of fuel assembly of fast reactors under high dose neutron irradiation
Kozolov, A.V.;Averin, A.S.;Brushkova, S.V. (Research and Development Inst. of Power Engineering, Zarechny, Sverdlovsk (Russian Federation));Kalashnic, G.V. (All Russian Research and Scientific Inst. of Inorganic Materials, Moscow (Russian Federation))
IAEA-TECDOC--1039, pp:211-221
Reprocessing of the irradiated boron carbide enriched by boron-10 isotope and its reuse in the control rods of the fast breeder reactors
Risovany, V.D.; Zakharov, A.V.; Klochkov, E.P.; Osipenko, A.G.; Kosulin, N.S.; Mikhailichenko, G.I. (Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation))
IAEA-TECDOC--884, pp:214-219
Hydrodynamic module validation of THEHYCO-3DT code
Korsun, A.S.; Vitruk, S.G. (Moscow Engineering Physics Institute, Moscow (Russian Federation)); Ushakov, P.A.; Gabrianovich, B.N. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:222-225
Study and choice of main characteristics of fast reactor - Effective minor actinide
burner
Krivitski, I.Yu.; Matveev, V.I.; Poplavski, V.M. (State Scientific Center, Inst. of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--907, pp:225-236
Special feature of temperature field formation in the system of interacting fuel subassemblies in fast reactor core
Bogatirjev, I.L.; Zhukov, A.V.; Mtjukhin, N.M.; Sorokin, A.P.; Ushakov, P.A. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:226-233
In-pile strength of austenitic steels for fast reactors fuel pin cladding
Popov, V.V. (Institute of Physics and Power Engineering, State Scientific Center, Obninsk (Russian Federation))
IAEA-TECDOC--1039, pp:231-238
Methods of statistical calculation of fast reactor core with account of influence of fuel assembly form change in process of campaign and other factors
Sorokin, G.A.; Zhukov, A.V.; Bogoslovskaya, G.P.; Sorokin, A.P. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:234-248
The approximate thermal-model-testing method for non-stationary temperature fields in central zones of fast reactor assemblies
Mikhin, V.I.; Matukhin, N.M. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:249-255
The problems of thermohydraulics of prospective fast reactor concepts
Sedov, A.A. (RRC Kurchatov Institute, Moscow (Russian Federation))
IAEA-TECDOC--1157, pp:256-264
Electronuclear programm of ITEP and collaboration of institutes of Russia
Shvedov O.V.
IAEA-TC--903.3, pp:283-293
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
Numerical simulation of fuel assembly thermohydraulics of fast reactors with the partial blockage of cross section under the coolant
Zhukov, A.V.; Sorokin, A.P. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:296-321
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
On some issues of thorium fuel cycle study
Troyanov, M.F. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))
IAEA-TECDOC--1319, pp:316-320
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 questions of liquid metal two-phase flow modelling in the FBR core channels
Martsiniouk, D.Ye.; Sorokin, A.P. (State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:322-341
On development of analytical closure relationships for local wall friction, heat and mass transfer coefficients for sub-channel codes
Kornienko, Y. (State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:342-358
Settlement substantiation of the passive devices shutdown fast reactors by trip the absorbing rod in case of anticipated accident
Portianoy, A.G.; Serdun, E.N.; Sorokin, A.P.; Uhov, V.A.; Egorov, V.S. (State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:359-369
Modelling problems of emergency natural convection heat removal in the upper plenum of fast reactors using water
Ushakov, P.A.; Sorokin, A.P. (State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:370-377
Natural convection as the way of heat removal from fast reactor core at cooldown regimes
Zhukov, A.V.; Kuzina, J.A.; Uhov, V.A.; Sorokin, G.A. (State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))
IAEA-TECDOC--1157, pp:396-427
Creation of nuclear data base up to 150 Mev and corresponding scaling approach for ADS
Yu. N. Shubin, E. V. Gai, A. V. Ignatyuk, V. P. Lunev
Institute of Physics and Power Engineering, 249020 Obninsk, Russia
IAEA-TC--903.3, pp:435-447
IPPE Results of accelerator driven system neutronic benchmark
Alexander Chebeskov , Victor Dekoussar and Valerii Korobeinikov
State Scientific Center of Russian Federation -Institute
of Physics and Power Engineering,
Obninsk, Kaluga Region, Russia
IAEA-TC--903.3, pp:533-562
Accumulation of long-lived activity and other characteristics of heavy metal liquid targets
Yu. N. Shubin, E. V. Gai, A. V. Ignatyuk, V. P. Lunev
IAEA-TC--903.3, pp:625-633
Moltensalt reactor technology & hybrid concepts for nuclear energy generation and transmutation
V.Ignatiev, P.Alekseev, S.Konakov, N.Ponomarev-Stepnoi, V.Prusakov, S.Subbotine
IAEA-TC--903.3, pp:635-647
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