Problems of abnormal dynamics of thermal hydraulic processes in prospective reactors with supercritical parameters of light water coolant
Saved in:
| Date: | 2021 |
|---|---|
| Main Authors: | I. H. Sharaievskyi, N. M. Fialko, A. V. Nosovskyi, L. B. Zimin, T. S. Vlasenko, H. I. Sharaievskyi |
| Format: | Article |
| Language: | English |
| Published: |
2021
|
| Series: | Nuclear power and the environment |
| Online Access: | http://jnas.nbuv.gov.ua/article/UJRN-0001403458 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| Journal Title: | Library portal of National Academy of Sciences of Ukraine | LibNAS |
Institution
Library portal of National Academy of Sciences of Ukraine | LibNASSimilar Items
Main directions of Russian development of prospective structures of water-cooled supercritical pressure reactors
by: I. H. Sharaievskyi, et al.
Published: (2020)
by: I. H. Sharaievskyi, et al.
Published: (2020)
World trends of construction development of water-cooled supercritical pressure reactors
by: I. H. Sharaevskyi, et al.
Published: (2020)
by: I. H. Sharaevskyi, et al.
Published: (2020)
Metalophysical problems of WWER reactor vessel welding joints reliability
by: I. H. Sharaievskyi, et al.
Published: (2022)
by: I. H. Sharaievskyi, et al.
Published: (2022)
Current physical problems of the dynamic damage in elements of the first circuit of VVER reactors
by: I. H. Sharaievskyi, et al.
Published: (2022)
by: I. H. Sharaievskyi, et al.
Published: (2022)
Study of WWER reactors neutronic noise spectral images in irregular thermohydraulic regimes of core zones
by: I. H. Sharaievskyi, et al.
Published: (2022)
by: I. H. Sharaievskyi, et al.
Published: (2022)
Evolution of thermophysical problems in constructions of VVVR reactors main circulation pumps
by: H. I. Sharaievskyi, et al.
Published: (2019)
by: H. I. Sharaievskyi, et al.
Published: (2019)
Prospective directions of increasing operating reliability and providing operational management of the npp main equipment resources
by: I. H. Sharaievskyi, et al.
Published: (2021)
by: I. H. Sharaievskyi, et al.
Published: (2021)
Specifics of the flow of supercritical water under conditions of mixed convection
by: N. M. Fialko, et al.
Published: (2018)
by: N. M. Fialko, et al.
Published: (2018)
Mathematical model of automatic recognition of latent pre-emergency conditions of shaft mechanical sealing systems of NPP main circulation pumps
by: A. V. Nosovskyi, et al.
Published: (2020)
by: A. V. Nosovskyi, et al.
Published: (2020)
Thermal hydraulic calculations of the WWR-SM research reactor
by: S. A. Baytelesov, et al.
Published: (2020)
by: S. A. Baytelesov, et al.
Published: (2020)
Thermal hydraulic method of optimizing the thermal resistance of nuclear fuel of reactor installations
by: V. I. Skalozubov, et al.
Published: (2024)
by: V. I. Skalozubov, et al.
Published: (2024)
Problems of the thermal-hydraulic computer codes perfection
by: I. G. Sharaevskij, et al.
Published: (2015)
by: I. G. Sharaevskij, et al.
Published: (2015)
Improvement of Reliability and Ecological Safety of NPP Reactor Coolant Pump Seals
by: S. Shevchenko, et al.
Published: (2020)
by: S. Shevchenko, et al.
Published: (2020)
Electron irradiation, temperature, and stress effect on corrosion of Zr-, Ni-Cr-, and Fe-Cr-based alloys in the vicinity of the water coolant supercritical transition
by: Bakai, O.S., et al.
Published: (2020)
by: Bakai, O.S., et al.
Published: (2020)
Electron irradiation of the material samples of new generation nuclear reactors in the supercritical water convection loop
by: Bakai, A.S., et al.
Published: (2013)
by: Bakai, A.S., et al.
Published: (2013)
Study of Heat Transfer Processes in Modelled Core of Nuclear Reactor with Helium Coolant
by: A. A. Avramenko, et al.
Published: (2017)
by: A. A. Avramenko, et al.
Published: (2017)
Effect of permeability of peble bed on heat transfer in the core of nuclear reactor with helium coolant
by: A. A. Avramenko, et al.
Published: (2017)
by: A. A. Avramenko, et al.
Published: (2017)
Comparison of statistical properties of coolant temperature and neutron flux in a reactor PWR-1000
by: A. D. Skorbun, et al.
Published: (2017)
by: A. D. Skorbun, et al.
Published: (2017)
Comparison of statistical properties of coolant temperature and neutron flux in a reactor PWR-1000
by: Skorbun, A.D., et al.
Published: (2017)
by: Skorbun, A.D., et al.
Published: (2017)
Computational dosimetry and post-irradiation studies of the electron beam irradiation-assisted corrosion and stress corrosion cracking of statically strained steel samples in a supercritical water coolant
by: Bakai, O.S., et al.
Published: (2022)
by: Bakai, O.S., et al.
Published: (2022)
Physical substantiation of the mechanical sealing systems automatic diagnostics problem of NPP coolant reactor pumps
by: A. V. Nosovskij, et al.
Published: (2019)
by: A. V. Nosovskij, et al.
Published: (2019)
Problems of calculation of heat transfer crisis in fuel assembles of water cooled reactors
by: G. I. Sharaevskij, et al.
Published: (2018)
by: G. I. Sharaevskij, et al.
Published: (2018)
Features of diagnostics of unsupposed thermal, vibroacoustic and neutron processes in the first contour of nuclear reactors
by: I. G. Sharaevskij, et al.
Published: (2018)
by: I. G. Sharaevskij, et al.
Published: (2018)
CFD modeling of heat transfer under flow of supercritical parameters water in vertical bare tubes
by: N. M. Fialko, et al.
Published: (2018)
by: N. M. Fialko, et al.
Published: (2018)
Problems of diagnostical ensuring of water-water energetic reactors' vibroacoustic safety (Rart 2)
by: N. M. Fialko, et al.
Published: (2016)
by: N. M. Fialko, et al.
Published: (2016)
Problems of diagnostical ensuring of water-water energetic reactors' vibroacoustic safety (Part I)
by: N. M. Fialko, et al.
Published: (2015)
by: N. M. Fialko, et al.
Published: (2015)
Self-sustained regime of nuclear burning wave in U–Pu fast reactor with Pb–Bi coolant
by: Fomin, S.P., et al.
Published: (2007)
by: Fomin, S.P., et al.
Published: (2007)
Energy efficiency of cooling systems of thermal stresses the most powerful turbo units with supercritical and supercritical steam parameters of the initial
by: Переверзев, Д. А., et al.
Published: (2016)
by: Переверзев, Д. А., et al.
Published: (2016)
Energy efficiency of cooling systems of thermal stresses the most powerful turbo units with supercritical and supercritical steam parameters of the initial
by: Переверзев, Д. А., et al.
Published: (2016)
by: Переверзев, Д. А., et al.
Published: (2016)
Energy efficiency of cooling systems of thermal stresses the most powerful turbo units with supercritical and supercritical steam parameters of the initial
by: D. A. Pereverzev, et al.
Published: (2011)
by: D. A. Pereverzev, et al.
Published: (2011)
Identification of parameters of the model of thermal and hydraulic processes in the crossflow heat exchanger, based on the analogy between thermal and hydraulic resistances
by: S. D. Vinnichuk, et al.
Published: (2018)
by: S. D. Vinnichuk, et al.
Published: (2018)
Thermal hydraulics verification safety studies to support the licensing of neutron source Accelerator Driven System
by: O. V. Kukhotskyi, et al.
Published: (2020)
by: O. V. Kukhotskyi, et al.
Published: (2020)
Supercritical water convection loop control system
by: Boriskin, V.N., et al.
Published: (2014)
by: Boriskin, V.N., et al.
Published: (2014)
Study of materials for reactors employing molten fluoride salts or PB-BI coolant using an electron irradiation test facility
by: Azhazha, V.M., et al.
Published: (2005)
by: Azhazha, V.M., et al.
Published: (2005)
Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant circuit of WWER-1000 reactor
by: Yu. V. Fylonych, et al.
Published: (2021)
by: Yu. V. Fylonych, et al.
Published: (2021)
Thermal-Hydraulic Safety Analysis of Mixed Core Loads for Ukrainian NPPs with VVER-1000
by: Yu. Yu. Vorobiov, et al.
Published: (2016)
by: Yu. Yu. Vorobiov, et al.
Published: (2016)
Directions of the development of nuclear power plants technologies. Part 1. Light-water reactors
by: Kovetskiy V.M., et al.
Published: (2006)
by: Kovetskiy V.M., et al.
Published: (2006)
Monitoring the flow rate of water in the supercritical convection loop
by: Bakai, A.S., et al.
Published: (2016)
by: Bakai, A.S., et al.
Published: (2016)
Dispenser for water sampling from supercritical convection loop
by: Boriskin, V.N., et al.
Published: (2014)
by: Boriskin, V.N., et al.
Published: (2014)
Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding
by: Zuyok, V., et al.
Published: (2022)
by: Zuyok, V., et al.
Published: (2022)
Similar Items
-
Main directions of Russian development of prospective structures of water-cooled supercritical pressure reactors
by: I. H. Sharaievskyi, et al.
Published: (2020) -
World trends of construction development of water-cooled supercritical pressure reactors
by: I. H. Sharaevskyi, et al.
Published: (2020) -
Metalophysical problems of WWER reactor vessel welding joints reliability
by: I. H. Sharaievskyi, et al.
Published: (2022) -
Current physical problems of the dynamic damage in elements of the first circuit of VVER reactors
by: I. H. Sharaievskyi, et al.
Published: (2022) -
Study of WWER reactors neutronic noise spectral images in irregular thermohydraulic regimes of core zones
by: I. H. Sharaievskyi, et al.
Published: (2022)