Contents

Physics of Atomic Nuclei

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Vol. 80, No. 8, 2017

A simultaneous English language translation of this journal is available from Pleiades Publishing, Ltd.
Distributed worldwide by Springer. Physics of Atomic Nuclei ISSN 1063-7788.

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Experimental Determination of the Effective Resonance Absorption Integrals of ²³⁸U and ¹⁵⁸Gd in Urania–Gadolinia Rods

Yu. V. Stogov and V. N. Prosyolkov p. 1333  abstract

Comprehensive Experiments on Subcritical Assemblies of Cascade Reactor Systems

N. V. Zavyalov, R. I. Il’kaev, V. F. Kolesov, I. A. Ivanin, A. K. Zhitnik, M. I. Kuvshinov, Yu. Ya. Nefedov, V. T. Punin, A. V. Tel’nov and V. Kh. Khoruzhi p. 1339  abstract

High-Sensitivity Fast Neutron Detector KNK-2-8M

A. S. Koshelev, L. Ye. Dovbysh, M. A. Ovchinnikov, G. N. Pikulina, Yu. M. Drozdov, S. V. Chuklyaev and Yu. N. Pepyolyshev p. 1348  abstract

Planned Destruction of Metal-Core Reactor: Simulation of Catastrophic Accidents and New Experimental Possibilities

S. V. Vorontsov, M. I. Kuvshinov, A. T. Narozhnyi, V. A. Popov, V. P. Solov’ev and V. I. Yuferev p. 1357  abstract

Parameters of a Pulsed Reactor for Pumping a Large-Size NPL

V. F. Kolesov, V. Kh. Khoruzhy, V. B. Grechushkin and A. A. Pikulev p. 1363  abstract

Numerical Simulation of Measurements during the Reactor Physical Startup at Unit 3 of Rostov NPP

V. A. Tereshonok, L. V. Kryakvin, V. A. Pitilimov, S. A. Karpov, V. I. Kulikov, N. M. Zhylmaganbetov, O. Yu. Kavun, A. I. Popykin, R. A. Shevchenko, S. A. Shevchenko and T. V. Semenova p. 1370  abstract

Application of Backward Differentiation Formulas to Neutron Kinetics Problems

V. G. Zimin and A. L. Cherezov p. 1377  abstract

Calculation of Prompt Fission Neutron Lifetimes by the Monte Carlo Method

E. A. Gomin, V. D. Davidenko, A. S. Zinchenko and I. K. Kharchenko p. 1387  abstract

Calculation of the Neutron Importance Function and the Delayed Neutron Effective Fraction by the Monte Carlo Method

E. A. Gomin, V. D. Davidenko, A. S. Zinchenko and I. K. Kharchenko p. 1392  abstract

Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method

E. A. Gomin, V. D. Davidenko, A. S. Zinchenko and I. K. Kharchenko p. 1399  abstract

Engineering Margin Factors Used in the Design of the VVER Fuel Cycles

M. P. Lizorkin and L. K. Shishkov p. 1408  abstract

Methodology of Calculation of Hypothetical Isomeric γ-Reactors by the Example of ^178m2Hf

V. F. Kolesov, S. N. Abramovich, A. E. Shmarov and E. V. Intjapina p. 1424  abstract

Natural Transmutation of Actinides via the Fission Reaction in the Closed Thorium–Uranium–Plutonium Fuel Cycle

V. Ye. Marshalkin and V. M. Povyshev p. 1433  abstract

Variants of Regenerated Fissile Materials Usage in Thermal Reactors as the First Stage of Fuel Cycle Closing

E. A. Andrianova and V. F. Tsibul’skiy p. 1443  abstract

A Possible Mechanism for Formation of Nonwettable “Dry Spots” on a Heated Surface during Nucleate Pool Boiling: II. Feedwater Stop Regime

Yu. M. Zhukov and D. S. Urtenov p. 1448  abstract

Interdiffusion of Mo and W in the Shells of Electrogenerating Channels under Reactor Irradiation

V. A. Churin, V. A. Koryukin and I. V. Vasil’ev p. 1458  abstract

Analysis of the Range of Applicability of Thermodynamic Calculations in the Engineering of Nitride Fuel Elements

A. S. Ivanov, A. A. Rusinkevich, G. V. Belov and Yu. A. Ivanov p. 1464  abstract

Some Thermodynamic Features of Uranium–Plutonium Nitride Fuel in the Course of Burnup

A. A. Rusinkevich, A. S. Ivanov, G. V. Belov and M. V. Skupov p. 1470  abstract

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