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                             24 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Advances in the Physical Start-Up Test Program for VVER-1200 Power Units Tsyganov, S. V.

87 8 p. 1039-1046
artikel
2 Application of Miniature Specimens for Off-Center Tension Aimed at Determination of Fracture Toughness of Steels of VVER-1000 Reactor Vessel in the Ductile–Brittle Transition Zone Bandura, A. P.

87 8 p. 1159-1165
artikel
3 Artificial Intelligence in the Field of Atomic Energy Usage—Existing Possibilities and Perspectives Nikolaeva, A. V.

87 8 p. 1020-1029
artikel
4 Code for Calculating Temperature Fields in RBMK KLADKA-2 Babaitsev, V. N.

87 8 p. 1114-1122
artikel
5 Container Materials for Molten Salt Nuclear Reactors: Problems and Research Abalin, A. S.

87 8 p. 1166-1175
artikel
6 Determination of the Characteristics of Neutron Field of the IGRIK-2 Reactor Using the Neutron Activation Method Baphaev, A. R.

87 8 p. 1073-1077
artikel
7 Development of the Physical and Technical Foundations of the Technology of High-Temperature Gas-Cooled Reactor Systems Fomichenko, P. A.

87 8 p. 993-1007
artikel
8 Experimental Study of Corrosion Resistance of Nickel-Molybdenum Alloys in the Melt of Lithium and Beryllium Fluoride Salts Surenkov, A. I.

87 8 p. 1176-1186
artikel
9 Experimental Study of the Gamma Component in the Rhodium SPD Signal Kochkin, V. N.

87 8 p. 1060-1063
artikel
10 Machine Learning Method for Validation of the Computational Model of Nonstationary Xenon Processes in the VVER Reactor Based on the Algorithm of Separation of Variables Nikolaev, A. L.

87 8 p. 1030-1038
artikel
11 Method of Homogenization of Group Neutronic Constants Taking into Account Heterogeneous and Kinetic Effects Vasekin, V. N.

87 8 p. 1078-1082
artikel
12 Numerical Simulation of Fluid Flow and Heat Transfer at Supercritical Pressures of Water Coolant for a Wire-Wrapped Rod Bundle Kukanov, V. Yu.

87 8 p. 1123-1137
artikel
13 Preliminary Calculated and Experimental Assessments of the Possibility of Using High-Nickel Steels for Pressure Vessels of Next Generation VVERs Kuleshova, E. A.

87 8 p. 1151-1158
artikel
14 PRIM-AES Software Package for Simulation of Transient Modes at Power Units with VVER Reactors Gornostaev, D. A.

87 8 p. 1089-1100
artikel
15 Procedure for Taking into Account the Influence of the Neutron Field on Reactivity Effects in Engineering Calculations Kresov, D. G.

87 8 p. 1083-1088
artikel
16 Radiation-Chemical Fixation of Nitrogen in an Aqueous Solution of H2 and N2 under Accelerated Proton Irradiation. Mathematical Model and Its Verification Kabakchi, S. A.

87 8 p. 1187-1194
artikel
17 Results of Numerical Simulation of Measurements of Scram Worth Performed during the Start-Up Phase of the Second and Third Fuel Loads of the Novovoronezh NPP Unit 6 Zhylmaganbetov, N. M.

87 8 p. 1047-1052
artikel
18 Self-Powered Neutron Detector with Hafnium Metal Emitter in VVER Reactors Kalinushkin, A. E.

87 8 p. 1064-1066
artikel
19 Statistical Component of Calibration Error of VVER In-Core Thermal Sensors Timonin, A. S.

87 8 p. 1067-1072
artikel
20 Study of the Properties of High-Sensitivity Self-Powered Neutron Detector Shikalov, V. F.

87 8 p. 1053-1059
artikel
21 The Fusion Neutron Source as Part of a Nuclear Energy System Andrianova, E. A.

87 8 p. 1008-1019
artikel
22 Trends of Structure Degradation of VVER-1000 Reactor Pressure Vessel Steels Determining Their Performance at Lifetimes of over 60 Years Kuleshova, E. A.

87 8 p. 1138-1150
artikel
23 Uncertainty in the Prediction of the Neutronic Characteristics of the RBMK Reactor Related to the Choice of the Graphite Stack Repair Scheme Plekhanov, R. V.

87 8 p. 1106-1113
artikel
24 Using (Np, Am) Fractions of Minor Actinides for 238Pu Production in a VVER-Type Reactor Shmelev, A. N.

87 8 p. 1101-1105
artikel
                             24 gevonden resultaten
 
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