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                             15 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analisys of safety system pumps conditions based on their testing results Leskin, S.T.
2017
3 2 p. 112-116
5 p.
artikel
2 Assessment of the critical condition for the operation of an IBR reactor with a subcritical unit in an equilibrium mode Brezhnev, A.I.
2017
3 2 p. 127-132
6 p.
artikel
3 Computer modeling of thermal processes involving calcium, strontium and cesium during radioactive graphite heating in the carbon dioxide atmosphere Barbin, N.M.
2017
3 2 p. 122-126
5 p.
artikel
4 Consideration of economic risks in a comparative analysis of nuclear technologies with different maturity levels Andrianov, A.A.
2017
3 2 p. 158-163
6 p.
artikel
5 Design and experimental assessment of thermal stratification effects on operational loading of surge line of Unit 5, Novovoronezh NPP Povarov, V.P.
2017
3 2 p. 92-97
6 p.
artikel
6 Development and application of the civil plutonium database in Russia Pshakin, G.M.
2017
3 2 p. 152-157
6 p.
artikel
7 Experimental estimation of the effect of contact condensation of steam–gas mixture on VVER passive safety systems operation Morozov, A.V.
2017
3 2 p. 98-104
7 p.
artikel
8 Experimental investigation of heat and mass exchange processes during operation of VVER steam generator in emergency condensing mode Shlyopkin, A.S.
2017
3 2 p. 105-111
7 p.
artikel
9 Experimental studies into the dependences of the axial lead coolant pump performance on the impeller cascade parameters Beznosov, A.V.
2017
3 2 p. 141-144
4 p.
artikel
10 Forecasting reliability of ShADR-32M coolant flow rate sensors Pereguda, A.I.
2017
3 2 p. 145-151
7 p.
artikel
11 Improving the general and ecological image of nuclear power Suzdaleva, A.L.
2017
3 2 p. 164-167
4 p.
artikel
12 Monte Carlo evaluation of neutron irradiation damage to the VVER-1000 RPV Ardekani, Seyed Fazel Ghazi
2017
3 2 p. 73-80
8 p.
artikel
13 Numerical investigation of Prandtl number effect on heat transfer and fluid flow characteristics of a nuclear fuel element Razak, R.K. Abdul
2017
3 2 p. 81-91
11 p.
artikel
14 Prediction of the moderator temperature field in a heavy water reactor based on a cellular neural network Starkov, S.O.
2017
3 2 p. 133-140
8 p.
artikel
15 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
3 2 p. 117-121
5 p.
artikel
                             15 gevonden resultaten
 
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