Algorithm for solving the linear Cauchy problem for large systems of ordinary differential equations with the use of parallel computations A. V. Moryakov OriginalPaper 17 February 2017 Pages: 1233 - 1241
LUCKY_TD code for solving the time-dependent transport equation with the use of parallel computations A. V. Moryakov OriginalPaper 17 February 2017 Pages: 1242 - 1245
Parallelization of heterogeneous reactor calculations on a graphics processing unit V. M. MalofeevV. A. Pal’shin OriginalPaper 17 February 2017 Pages: 1246 - 1251
Time-dependent integral equations of neutron transport for calculating the kinetics of nuclear reactors by the Monte Carlo method V. D. DavidenkoA. S. ZinchenkoI. K. Harchenko OriginalPaper 17 February 2017 Pages: 1252 - 1256
Effective conditions for the neutron flux density at axial boundaries of the core E. A. AristarkhovaV. M. Malofeev OriginalPaper 17 February 2017 Pages: 1257 - 1260
Generalization of two-dimensional DDL schemes of the GQ method for three-dimensional arbitrary hexahedral spatial mesh A. A. Nikolaev OriginalPaper 17 February 2017 Pages: 1261 - 1266
Criticality calculation of non-ordinary systems A. V. KaluginV. V. Tebin OriginalPaper 17 February 2017 Pages: 1267 - 1278
Shaping of the axial power density distribution in the core to minimize the vapor volume fraction at the outlet of the VVER-1200 fuel assemblies V. I. SavanderB. E. ShumskiyA. A. Pinegin OriginalPaper 17 February 2017 Pages: 1279 - 1289
On the equilibrium isotopic composition of the thorium–uranium–plutonium fuel cycle V. Ye. MarshalkinV. M. Povyshev OriginalPaper 17 February 2017 Pages: 1290 - 1297
The influence of changes in the VVER-1000 fuel assembly shape during operation on the power density distribution L. K. ShishkovS. S. GorodkovA. S. Sumarokova OriginalPaper 17 February 2017 Pages: 1298 - 1304
Analysis of the uncertainties in the physical calculations of water-moderated power reactors of the VVER type by the parameters of models of preparing few-group constants V. V. BryukhinK. Yu. KurakinM. A. Uvakin OriginalPaper 17 February 2017 Pages: 1305 - 1314
Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle A. S. LubinaA. S. SubbotinA. A. Frolov OriginalPaper 17 February 2017 Pages: 1315 - 1324
A method for development of efficient 3D models for neutronic calculations of ASTRA critical facility using experimental information A. L. BalaninV. F. BoyarinovYu. N. Volkov OriginalPaper 17 February 2017 Pages: 1325 - 1332
Measuring the efficiency of control rods in the RBMK critical assembly using a model of RKI-1 reactimeter V. E. ZhitarevG. V. LebedevA. Yu. Sergevnin OriginalPaper 17 February 2017 Pages: 1333 - 1339
Feasibility of creating a specialized reactimeter based on the inverse solution to kinetics equation with a current-mode neutron detector A. S. KoshelevA. V. ArapovM. A. Ovchinnikov OriginalPaper 17 February 2017 Pages: 1340 - 1348
Wide-range structurally optimized channel for monitoring the certified power of small-core reactors A. S. KoshelevK. N. KovshovA. B. Sokolov OriginalPaper 17 February 2017 Pages: 1349 - 1356
Measurement of prompt neutron generation time at the VIR-2M pulsed nuclear reactor L. Yu. GlukhovS. P. KotkovS. S. Chursin OriginalPaper 17 February 2017 Pages: 1357 - 1361
A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors A. V. BushuevA. F. KozhinV. E. Smirnov OriginalPaper 17 February 2017 Pages: 1362 - 1366