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                             18 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analysis of the Range of Applicability of Thermodynamic Calculations in the Engineering of Nitride Fuel Elements Ivanov, A. S.
2017
80 8 p. 1464-1469
artikel
2 Application of Backward Differentiation Formulas to Neutron Kinetics Problems Zimin, V. G.
2017
80 8 p. 1377-1386
artikel
3 Calculation of Prompt Fission Neutron Lifetimes by the Monte Carlo Method Gomin, E. A.
2017
80 8 p. 1387-1391
artikel
4 Calculation of the Neutron Importance Function and the Delayed Neutron Effective Fraction by the Monte Carlo Method Gomin, E. A.
2017
80 8 p. 1392-1398
artikel
5 Comprehensive Experiments on Subcritical Assemblies of Cascade Reactor Systems Zavyalov, N. V.
2017
80 8 p. 1339-1347
artikel
6 Engineering Margin Factors Used in the Design of the VVER Fuel Cycles Lizorkin, M. P.
2017
80 8 p. 1408-1423
artikel
7 Experimental Determination of the Effective Resonance Absorption Integrals of 238U and 158Gd in Urania–Gadolinia Rods Stogov, Yu. V.
2017
80 8 p. 1333-1338
artikel
8 High-Sensitivity Fast Neutron Detector KNK-2-8M Koshelev, A. S.
2017
80 8 p. 1348-1356
artikel
9 Interdiffusion of Mo and W in the Shells of Electrogenerating Channels under Reactor Irradiation Churin, V. A.
2017
80 8 p. 1458-1463
artikel
10 Methodology of Calculation of Hypothetical Isomeric γ-Reactors by the Example of 178m2Hf Kolesov, V. F.
2017
80 8 p. 1424-1432
artikel
11 Natural Transmutation of Actinides via the Fission Reaction in the Closed Thorium–Uranium–Plutonium Fuel Cycle Marshalkin, V. Ye.
2017
80 8 p. 1433-1442
artikel
12 Numerical Simulation of Measurements during the Reactor Physical Startup at Unit 3 of Rostov NPP Tereshonok, V. A.
2017
80 8 p. 1370-1376
artikel
13 Parameters of a Pulsed Reactor for Pumping a Large-Size NPL Kolesov, V. F.
2017
80 8 p. 1363-1369
artikel
14 Planned Destruction of Metal-Core Reactor: Simulation of Catastrophic Accidents and New Experimental Possibilities Vorontsov, S. V.
2017
80 8 p. 1357-1362
artikel
15 Possible Mechanism for Formation of Nonwettable “Dry Spots” on a Heated Surface during Nucleate Pool Boiling: II. Feedwater Stop Regime Zhukov, Yu. M.
2017
80 8 p. 1448-1457
artikel
16 Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method Gomin, E. A.
2017
80 8 p. 1399-1407
artikel
17 Some Thermodynamic Features of Uranium–Plutonium Nitride Fuel in the Course of Burnup Rusinkevich, A. A.
2017
80 8 p. 1470-1475
artikel
18 Variants of Regenerated Fissile Materials Usage in Thermal Reactors as the First Stage of Fuel Cycle Closing Andrianova, E. A.
2017
80 8 p. 1443-1447
artikel
                             18 gevonden resultaten
 
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