Search Results - "Kandiev, Ya"

PRIZMA-DSP Code Calculations of the Fission-Point Distribution in the OECD/NEA Test3 and Test4 Systems by Kandiev, Ya. Z., Lobanov, L. V., Serova, E. V.

“…A method implemented in the PRIZMA-DSP code was developed for calculating multiplying systems with weak couplings [1, 2]. In the course of the development of…”
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Prizma-DSP Code Calculations of the Fission-Point Distribution in the OECD/NEA Proposed Test2 System by Kandiev, Ya. Z., Lobanova, L. V., Serova, E. V.

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PRIZM-DSP Code Calculations of Fission Point Distribution in the Test1 System Proposed by OECD/NEA by Kandiev, Ya. Z., Lobanova, L. V., Serova, E. V.

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Monte-Carlo Method of Calculating Weakly Coupled Systems Using the PRIZMA-DSP Code by Kandiev, Ya. Z., Lobanova, L. V., Orlov, V. G., Serova, E. V.

“…A Monte Carlo method implemented in the PRIZMA-DSP code to calculate multiplying systems, including weakly coupled systems, is described. In the code, the…”
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Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code by Kandiev, Ya, Kashaeva, E., Malyshkin, G., Bayanov, B., Taskaev, S.

“…At Budker Institute of Nuclear Physics, epithermal neutron source for neutron-capture therapy was built and neutron generation was realized. Source is based on…”
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A protective subsurface container for holding and temporary storage of activated targets by Bayanov, B. F., Kandiev, Ya. Z., Kashaeva, E. A., Malyshkin, G. N., Taskaev, S. Yu, Chudaev, V. Ya

“…An accelerator-driven source of epithermal neutrons has been developed by the Budker Institute of Nuclear Physics for carrying out investigations into neutron…”
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Background determination for the neutron–neutron scattering experiment at the reactor YAGUAR by Muzichka, A.Yu, Furman, W.I., Lychagin, E.V., Krylov, A.R., Nekhaev, G.V., Sharapov, E.I., Shvetsov, V.N., Strelkov, A.V., Levakov, B.G., Lyzhin, A.E., Chernukhin, Yu.I., Kandiev, Ya.Z., Howell, C.R., Mitchell, G.E., Crawford, B.E., Stephenson, S.L., Tornow, W.

“…The motivation and design is outlined for the experiment to measure the neutron–neutron singlet scattering length directly with thermal neutrons at the pulsed…”
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Validation of nuclear and radiation safety of a container for spent AMB reactor fuel assemblies at the beloyarskaya nuclear power plant by GORIN, N. V, KANDIEV, Ya. Z, CHERNUKHIN, Yu. I

“…An approach is proposed for validating the nuclear and radiation safety of a container for spent fuel assemblies from AMB-100 and-200 reactors at the…”
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Method for identifying 17-place casings with spent fuel assemblies of AMB reactors at the Beloyarskaya nuclear power plant by Gorin, N V, Kandiev, YaZ, Lipilina, EN, Rukavishnikov, G V, Churikov, YuI, Gizzatulin, KhF, Khomchenko, AN

“…A method is proposed for identifying a cylindrical case with a jacket containing 17 spent fuel assemblies from the AMB reactors at the Beloyarskaya nuclear…”
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Investigation of an Electromagnetic Pulse Generated by a System on a Standard Spacecraft by Lazarev, Yu N, Petrov, P V, Diyankova, E V, Vronskii, A V, Kandiev, Ya Z

“…Results on generation of an electromagnetic pulse on a spacecraft under the action of X-ray and gamma radiation are described. The computational technology…”
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Estimates of electron-positron pair production in the interaction of high-power laser radiation with high-Z targets by Gryaznykh, D. A., Kandiev, Ya. Z., Lykov, V. A.

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High-efficiency multi-wire tungsten moderator for slow positron source on SPring-8 hard synchrotron radiation by Plokhoi, V.V, Z. Kandiev, Ya, Samarin, S.I, Malyshkin, G.N, Baidin, G.V, Litvinenko, I.A, Nikitin, V.P

“…The paper provides results of numeric simulations of in-target positron production process, processes of moderation, thermalization, diffusion, and reemission…”
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Determination of the Neutron Flux of the NG-12I Neutron Generator by Litvin, V. I., Kandiev, Ya. Z., Malyshkin, G. N., Kashaeva, E. A., Samarin, S. I., Mokichev, G. V.

“…We describe a method of determining the neutron flux of an NG-12I neutron generator, using Al and F activation detectors. The numerical computation data used…”
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Estimation of the Effect of Small Perturbations in Multivariant Calculations Using the Prizma-D Computer Program by Kandiev, Ya. Z., Malakhov, A. A., Serova, E. V., Spirina, S. G.

“…In eigenvalue problems, in contrast to problems with a fixed source, the perturbation introduced into the system affects the distribution of the fission points…”
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Tagged Particles in Monte Carlo Calculations of Radiation Transfer Using the Prizma Computer Program by Kandiev, Ya. Z., Serova, E. V.

“…The additional possibilities due to the introduction into the PRIZMA program, intended for performing Monte Carlo calculations of linear radiation transfer…”
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Calibration Experiment on the Detection of Fissioning Material in Soil by Means of Neutron Detection by Gorin, N. V., Zakharov, V. V., Kandiev, Ya. Z., Lipilina, E. N., Pokatashkin, A. P., Rukavishnikov, G. V., Ul'yanov, A. I., Shmakov, D. V., Shcherbina, A. N.

“…(ProQuest: Abstract omitted; see image)[PUBLICATION ABSTRACT]…”
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Computational-Experimental Study of the Heating of Structural Materials by IGRIK Radiation by Gorin, N. V., Kandiev, Ya. Z., Kedrov, A. V., Levakov, B. G., Lipilina, E. N., Lyutov, V. D., Mingazov, O. A., Pilipenko, D. E., Rukavishnikov, G. V., Serova, E. V., Turkin, D. V., Ul’yanov, A. I., Shmakov, D. V., Shcherbina, A. N., Vasil’ev, A. P.

“…An experiment measuring the temperature to which small samples of W, Ta, Mo, Cu, Zr, Ni, Fe, Ti, Sn, and Pb are heated by IGRIK radiation is performed. The…”
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Computational Investigation of the Lifetime Characteristics of IGR Neutrons by Gorin, N. V., Kandiev, Ya. Z., Kashaeva, E. A., Shcherbina, A. N., Gaidaichuk, V. A., Demko, N. A., Kaz'min, Yu. M., Vasil'ev, A. P., Pavshuk, V. A.

“…It is shown computationally that the IGR neutron lifetime depends on the neutron creation location in the core and that the absorbing material of the control…”
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Monitoring of the movement of a melt of fissioning material in the experimental channel of a pulsed graphite reactor igr using small neutron detectors by GORIN, N. V, KANDIEV, Ya. Z, SHCHERBINA, A. N, ZHOTABAEV, Zh. R, KAZ'MIN, Yu. M, PAKHNITS, V. A, VASIL'EV, A. P, MALINKIN, V. M, PAVSHUK, V. A, NIKIPORETS, Yu. G

“…It is shown that fuel elements consisting of a fissioning material can be simulated from the standpoint of the influence on the characteristics of the neutron…”
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PRIZMA.D computational investigation of physical processes in the IGR reactor by Gorin, N. V., Kandiev, Ya. Z., Kaz’min, Yu. M.

“…It is shown for one experiment that the physical processes occurring in the-core of a pulsed uranium-graphite reactor IGR can be investigated by a…”
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