Experimental Determination of the Effective Resonance Absorption Integrals of 238U and 158Gd in Urania–Gadolinia Rods Yu. V. StogovV. N. Prosyolkov OriginalPaper 10 March 2018 Pages: 1333 - 1338
Comprehensive Experiments on Subcritical Assemblies of Cascade Reactor Systems N. V. ZavyalovR. I. Il’kaevV. Kh. Khoruzhi OriginalPaper 10 March 2018 Pages: 1339 - 1347
High-Sensitivity Fast Neutron Detector KNK-2-8M A. S. KoshelevL. Ye. DovbyshYu. N. Pepyolyshev OriginalPaper 10 March 2018 Pages: 1348 - 1356
Planned Destruction of Metal-Core Reactor: Simulation of Catastrophic Accidents and New Experimental Possibilities S. V. VorontsovM. I. KuvshinovV. I. Yuferev OriginalPaper 10 March 2018 Pages: 1357 - 1362
Parameters of a Pulsed Reactor for Pumping a Large-Size NPL V. F. KolesovV. Kh. KhoruzhyA. A. Pikulev OriginalPaper 10 March 2018 Pages: 1363 - 1369
Numerical Simulation of Measurements during the Reactor Physical Startup at Unit 3 of Rostov NPP V. A. TereshonokL. V. KryakvinT. V. Semenova OriginalPaper 10 March 2018 Pages: 1370 - 1376
Application of Backward Differentiation Formulas to Neutron Kinetics Problems V. G. ZiminA. L. Cherezov OriginalPaper 10 March 2018 Pages: 1377 - 1386
Calculation of Prompt Fission Neutron Lifetimes by the Monte Carlo Method E. A. GominV. D. DavidenkoI. K. Kharchenko OriginalPaper 10 March 2018 Pages: 1387 - 1391
Calculation of the Neutron Importance Function and the Delayed Neutron Effective Fraction by the Monte Carlo Method E. A. GominV. D. DavidenkoI. K. Kharchenko OriginalPaper 10 March 2018 Pages: 1392 - 1398
Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method E. A. GominV. D. DavidenkoI. K. Kharchenko OriginalPaper 10 March 2018 Pages: 1399 - 1407
Engineering Margin Factors Used in the Design of the VVER Fuel Cycles M. P. LizorkinL. K. Shishkov OriginalPaper 10 March 2018 Pages: 1408 - 1423
Methodology of Calculation of Hypothetical Isomeric γ-Reactors by the Example of 178m2Hf V. F. KolesovS. N. AbramovichE. V. Intjapina OriginalPaper 10 March 2018 Pages: 1424 - 1432
Natural Transmutation of Actinides via the Fission Reaction in the Closed Thorium–Uranium–Plutonium Fuel Cycle V. Ye. MarshalkinV. M. Povyshev OriginalPaper 10 March 2018 Pages: 1433 - 1442
Variants of Regenerated Fissile Materials Usage in Thermal Reactors as the First Stage of Fuel Cycle Closing E. A. AndrianovaV. F. Tsibul’skiy OriginalPaper 10 March 2018 Pages: 1443 - 1447
Possible Mechanism for Formation of Nonwettable “Dry Spots” on a Heated Surface during Nucleate Pool Boiling: II. Feedwater Stop Regime Yu. M. ZhukovD. S. Urtenov OriginalPaper 10 March 2018 Pages: 1448 - 1457
Interdiffusion of Mo and W in the Shells of Electrogenerating Channels under Reactor Irradiation V. A. ChurinV. A. KoryukinI. V. Vasil’ev OriginalPaper 10 March 2018 Pages: 1458 - 1463
Analysis of the Range of Applicability of Thermodynamic Calculations in the Engineering of Nitride Fuel Elements A. S. IvanovA. A. RusinkevichYu. A. Ivanov OriginalPaper 10 March 2018 Pages: 1464 - 1469
Some Thermodynamic Features of Uranium–Plutonium Nitride Fuel in the Course of Burnup A. A. RusinkevichA. S. IvanovM. V. Skupov OriginalPaper 10 March 2018 Pages: 1470 - 1475