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                             44 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Advanced nuclear fuel cycle for the RF using actinides breeding in thorium blankets of fusion neutron source Kulikov, G.G.
2016
2 p. 147-150
4 p.
artikel
2 Analisys of safety system pumps conditions based on their testing results Leskin, S.T.
2017
2 p. 112-116
5 p.
artikel
3 Application of multi-objective and robust optimization methods for a comparative evaluation of nuclear energy system deployment scenarios Andrianov, A.A.
2016
2 p. 102-107
6 p.
artikel
4 Assessment of the critical condition for the operation of an IBR reactor with a subcritical unit in an equilibrium mode Brezhnev, A.I.
2017
2 p. 127-132
6 p.
artikel
5 Comparison of histograms in physical research Bityukov, S.I.
2016
2 p. 108-113
6 p.
artikel
6 Computational and experimental studies of the causes of crack network formation in the area of the heat exchanger tube sheet in the BN'600 reactor Vilenskij, O. Yu.
2015
2 p. 83-87
5 p.
artikel
7 Computational and experimental study of an irradiation rig with a fuel heater for the BOR-60 reactor Varivtsev, A.V.
2016
2 p. 126-131
6 p.
artikel
8 Computer modeling of thermal processes involving calcium, strontium and cesium during radioactive graphite heating in the carbon dioxide atmosphere Barbin, N.M.
2017
2 p. 122-126
5 p.
artikel
9 Concerning hydrogen production based on nuclear technologies Khorasanov, G.L.
2015
2 p. 126-129
4 p.
artikel
10 Consideration of economic risks in a comparative analysis of nuclear technologies with different maturity levels Andrianov, A.A.
2017
2 p. 158-163
6 p.
artikel
11 Corner neutronic code Bereznev, V.P.
2015
2 p. 117-121
5 p.
artikel
12 Design and experimental assessment of thermal stratification effects on operational loading of surge line of Unit 5, Novovoronezh NPP Povarov, V.P.
2017
2 p. 92-97
6 p.
artikel
13 Development and application of the civil plutonium database in Russia Pshakin, G.M.
2017
2 p. 152-157
6 p.
artikel
14 Development and verification of a software system for the probabilistic safety analysis of nuclear plants as part of the proryv project Abramov, L.V.
2016
2 p. 77-80
4 p.
artikel
15 Development and verification of the TR-BN software for substantiation of normal operation modes of BN reactors Fadeev, I.D.
2016
2 p. 85-90
6 p.
artikel
16 Effects of impurities on heat transfer in lead coolants Belozerov, V.I.
2016
2 p. 132-135
4 p.
artikel
17 Effects of inorganic ligands on the efficiency of ion-exchange treatment of radioactive waste Chugunov, A.S.
2015
2 p. 107-110
4 p.
artikel
18 Ensuring the corrosion resistance of steels in heavy liquid metal coolants Legkikh, A.Yu.
2016
2 p. 136-141
6 p.
artikel
19 Evolution of the CYCLE code for the system analysis of the nuclear fuel cycle Kalashnikov, A.G.
2016
2 p. 114-118
5 p.
artikel
20 Examination of Silicon-28 and Uranium-235 resonance parameters based on integral and differential experiments Andrianova, O.N.
2016
2 p. 97-101
5 p.
artikel
21 Experience in using computer technologies for university training of future NPP personnel based on “University-Enterprise” program Semenov, V.K.
2015
2 p. 135-138
4 p.
artikel
22 Experimental estimation of the effect of contact condensation of steam–gas mixture on VVER passive safety systems operation Morozov, A.V.
2017
2 p. 98-104
7 p.
artikel
23 Experimental investigation of heat and mass exchange processes during operation of VVER steam generator in emergency condensing mode Shlyopkin, A.S.
2017
2 p. 105-111
7 p.
artikel
24 Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation Khafizov, R.R.
2015
2 p. 147-152
6 p.
artikel
25 Experimental studies into the dependences of the axial lead coolant pump performance on the impeller cascade parameters Beznosov, A.V.
2017
2 p. 141-144
4 p.
artikel
26 Experimental substantiation of selection of fuel channel imitator for hydrodynamic model of nuclear reactor Avdeev, E.F.
2015
2 p. 139-146
8 p.
artikel
27 Fast-neutron heterogeneous scintillation detector with high discrimination of gamma background Chernukhin, Yuri I.
2015
2 p. 130-134
5 p.
artikel
28 Flow and heat transfer in fuel rod bundles of water-cooled reactors with modified cell-type spacer grids Krapivtsev, V.G.
2015
2 p. 153-157
5 p.
artikel
29 Forecasting reliability of ShADR-32M coolant flow rate sensors Pereguda, A.I.
2017
2 p. 145-151
7 p.
artikel
30 Formation of proliferation-resistant nuclear fuel supplies based on reprocessed uranium for Russian nuclear technologies recipient countries Fedorov, M.I.
2015
2 p. 111-116
6 p.
artikel
31 Ideology and problems of systems and economic optimization of NPPs Klimenko, A.V.
2016
2 p. 142-146
5 p.
artikel
32 Improving the general and ecological image of nuclear power Suzdaleva, A.L.
2017
2 p. 164-167
4 p.
artikel
33 Interactive information system for simulation and visualization of nuclear transformations–Nuclear evolution software Dogov, A.A.
2016
2 p. 91-96
6 p.
artikel
34 Monte Carlo evaluation of neutron irradiation damage to the VVER-1000 RPV Ardekani, Seyed Fazel Ghazi
2017
2 p. 73-80
8 p.
artikel
35 Numerical investigation of Prandtl number effect on heat transfer and fluid flow characteristics of a nuclear fuel element Razak, R.K. Abdul
2017
2 p. 81-91
11 p.
artikel
36 On immobilization of high-level waste in an Y–Al garnet-based cermet matrix in SHS conditions Konovalov, E.E.
2015
2 p. 103-106
4 p.
artikel
37 Prediction of the moderator temperature field in a heavy water reactor based on a cellular neural network Starkov, S.O.
2017
2 p. 133-140
8 p.
artikel
38 Radiation characteristics of REMIX fuel during multiple recycling in VVER-1000 reactors Postovarova, D.V.
2016
2 p. 119-125
7 p.
artikel
39 Spectra of leakage neutrons from a Pb–Li spherical shell with central 252Cf and 14 MeV neutron sources and verification of evaluated neutron data Blokhin, A.I.
2015
2 p. 122-125
4 p.
artikel
40 Study of functional characteristics for safety system check valve using scaled model Baluyev, D.E.
2015
2 p. 99-102
4 p.
artikel
41 Swelling of improved 16Cr–15Ni–2Mo–Mn–Ti–V–B steel under dose rates from 1×10− 8 to 1.7×10− 6 dpa/s Kinev, E.A.
2017
2 p. 117-121
5 p.
artikel
42 Swelling of safety rod guide tubes in nonuniform fields of temperature and irradiation Porollo, S.I.
2015
2 p. 88-92
5 p.
artikel
43 The high-dose and high-temperature monitors of reactor irradiation based on insulators Stepanov, V.A.
2015
2 p. 93-98
6 p.
artikel
44 Turbine generator status diagnostic system based on petri nets Kachur, S.A.
2016
2 p. 81-84
4 p.
artikel
                             44 gevonden resultaten
 
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