Výsledky vyhledávání - "O. E. Stepanov"

Analysis of the Sensitivity and Uncertainty of Calculation Using the KORSAR/GP Code for Accidents with a Failure of Storage Pools’ Cooling System

Autor: V. E. Karnaukhov, M. M. Bedretdinov, P. S. Gagulin, R. M. Sledkov, O. E. Stepanov

Publikováno v: Thermal Engineering. 70:339-345

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9906ee716d5c1441176d2807c45afef5
https://doi.org/10.1134/s0040601523050026

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Verification of the TIGRSP Computer Code as Applied to a 19-Rod Fuel Assembly Using CFD Computations

Autor: S. S. Melekh, A. A. Pronin, O. E. Stepanov, I. Yu. Galkin, M. M. Kurnosov

Publikováno v: Thermal Engineering. 66:457-464

For assessing the core critical heat flux ratio in VVER-type nuclear reactors, the lattice computation code TIGRSP (steady-state thermal and hydraulic analysis of parameters in fuel rod bundles) is used. Despite the fact that quite a large amount of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a961b98bbbbae73d9ea60d1b3a8d241b
https://doi.org/10.1134/s0040601519070097

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Determination of the steam volume fraction in the event of loss of cooling of the spent fuel storage pool

Autor: N. A. Strebnev, O. E. Stepanov, R. M. Sledkov, I. Yu. Galkin

Publikováno v: Thermal Engineering. 64:15-19

When one solves engineering problems related to the cooling of fuel assemblies (FAs) in a spent fuel storage pool (SFSP) and the assessment of nuclear safety of FA storage in an SFSP in the initial event of loss of SFSP cooling, it is essential to de

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3825ab0d1264903d2deaccf2f3fe6387
https://doi.org/10.1134/s0040601516100098

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Modeling the transport of nitrogen in an NPP-2006 reactor circuit

Autor: S. S. Melekh, N. A. Strebnev, O. E. Stepanov, I. Yu. Galkin, R. M. Sledkov

Publikováno v: Thermal Engineering. 63:511-515

Efficient radiation protection of the public and personnel requires detecting an accident-initiating event quickly. Specifically, if a heat-exchange tube in a steam generator is ruptured, the 16N radioactive nitrogen isotope, which contributes to a s

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::19ed147e0b2f52fc7b5628f37c54d0d1
https://doi.org/10.1134/s0040601516030125

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A comparative analysis of the calculation methods of the heat emission during heating water with underheating

Autor: O. E. Stepanov, M. L. Lukashenko, V. E. Karnaukhov, O. V. Logashev, Yu. N. Eikhorn, I. M. Dikarev, A. V. Bulanov, A. M. Khudyakov

Publikováno v: Thermal Engineering. 61:203-209

Several relationships were analyzed to calculate the heat transfer during boiling water with underheating involving these implemented in RELAP5 and KORSAR codes. The errors of the presented relationships are evaluated using modeling of the experiment

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3d1dbf54183b79d2dc30c2e3097e15e6
https://doi.org/10.1134/s0040601513080089

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Stability of the water-chemistry regime in the loop of a passive safety system of nuclear power reactors

Autor: S. A. Kabakchi, M. L. Lukashenko, A. O. Verkhovskaya, A. V. Bulanov, V. E. Karnaukhov, O. E. Stepanov

Publikováno v: Atomic Energy. 108:97-102

The organization of the water-chemistry regime in the loop of a passive safety system, whose purpose is emergency removal of heat from the core of a nuclear power reactor, is examined. It is shown that a selfregulated water-chemistry regime in which

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2e13b8f3737b77e21fd106c21fd9c509
https://doi.org/10.1007/s10512-010-9262-7

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A comparison of procedures for estimating the impact of nondensable gases on steam condensation taking into account the interaction of power engineering processes in the primary circuit of a nuclear power installation

Autor: O. E. Stepanov, A. V. Bulanov, M. L. Lukashenko, Yu. B. Vorob’ev, V. E. Karnaukhov

Publikováno v: Thermal Engineering. 53:699-705

We consider two procedures for evaluating the influence of nondensables on steam condensation taking into account the integral effect from interaction between the water-chemistry and thermal-hydrodynamic processes occurring in the primary coolant cir

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9f8da76afc789cc114df68753f7763e1
https://doi.org/10.1134/s0040601506090060

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Simulation of the first-loop water chemistry regime of a nuclear power system with a two-phase water coolant

Autor: M. L. Lukashenko, O. E. Stepanov, S. A. Kabakchi, V. E. Karnaukhov, V. N. Pepa, Yu. B. Vorob’ev, A. V. Bulanov, A. O. Verkhovskaya

Publikováno v: Atomic Energy. 100:20-25

An approach to simulating the water-chemistry regime for transient and stationary operating states of a nuclear power system is proposed. The approach is based on the designer’s philosophy. The first loop of the nuclear power system is divided into

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::b0dce2790ee4b8929b167bb5e8286cd6
https://doi.org/10.1007/s10512-006-0044-1

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