Experimental and computational investigations of heat and mass transfer of intensifier grids
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L. L. Kobzar
Abstract
The paper discusses experimental and numerical investigations on intensification of thermal and mass exchange which were performed by National Research Centre “Kurchatov Institute” over the past years. Because of enhancing the power of active power plants, intensification of thermal and mass exchange investigations are performed by a number of Russian research and design organizations. Recently, many designs of heat mass transfer intensifier grids have been proposed. NRC “Kurchatov Institute” has accomplished a large scope of experimental investigations to study efficiency of intensifier grids of various types. The outcomes of experimental investigations can be used in verification of computational models and codes. On the basis of experimental data, we derived correlations to calculate coolant mixing and critical heat flux mixing in rod bundles equipped with intensifier grids. The acquired correlations were integrated in subchannel code SC-INT.
Kurzfassung
Die Ergebnisse der experimentellen und analytischen Arbeiten des Forschungszentrums „Kurchatov Institut“ in Russland zur Intensivierung des Wärmeübergangs und des Massenaustausches der letzten Jahre werden in diesem Beitrag zusammengefasst. Diese Arbeiten wurden durchgeführt, um die Leistungserhöhung derzeitiger in Betrieb befindlicher KKW zu unterstützen. Dazu wurden vielfältige Abstandshalterdesigns entwickelt. Diese wurden experimentell getestet. Die daraus entwickelten Korrelationen zur Berechnung der Kühlmittelvermischung und der kritischen Wärmeströme in Brennstabbündeln mit Abstandshaltern wurden in das Programm SC-INT eingebaut. Das Programm wurde anhand der Daten verifiziert.
References
1 Ryzhov, S. B.; Mokhov, V. A.; Vasilchenko, I. N. et. al.: Experience in operation of new fuel assemblies and prospects of development of fuel cycles NPP VVER. 7th International Scientific and Technical Conference “Safety, efficiency and economy of nuclear energy.” Moscow, May 2010 (Rus)Suche in Google Scholar
2 Babenko, Y. N.; Vereshchak, V. G.; Ivanov, A. V. etal.: Grid structure for a fuel assembly of a nuclear reactor. RF patent number 2389091, 2010 (Rus)Suche in Google Scholar
3 Astahov, V. I.; Bezrukov, Yu. A.; Logvinov, S. A.; Brantov, V. G.: Investigation of the influence of axial heat profile of the CHF in rod bundles. Proceedings of seminar “Thermal Physics – 78”, b. 2. Budapest, 1978Suche in Google Scholar
4 Kobzar, L. L.; Oleksyuk, D. A.: Development and verification program SC-1, designed for thermal-hydraulic subchannel calculation PWR cores. Second All-Russian Scientific and Technical Conference “Safety Assurance of NPP with WWER”, Podolsk, November 2001. (Rus)Suche in Google Scholar
© 2015, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2014
- Technical Contributions/Fachbeiträge
- Assessment of the uncertainties of MULTICELL calculations by the OECD NEA UAM PWR pin cell burnup benchmark
- Development of codes and KASKAD complex
- Applying full multigroup cell characteristics from MCU code to finite difference calculations of neutron field in VVER core
- Calculations of 3D full-scale VVER fuel assembly and core models using MCU and BIPR-7A codes
- An analysis of reactivity prediction during the reactor start-up process
- Experimental and computational investigations of heat and mass transfer of intensifier grids
- Implementation of CFD module in the KORSAR thermal-hydraulic system code
- Numerical and experimental investigation of 3D coolant temperature distribution in the hot legs of primary circuit of reactor plant with WWER-1000
- Analyses of Beyond Design Basis Accident Homogeneous Boron Dilution Scenarios
- Analysis of heterogeneous boron dilution transients during outages with APROS 3D nodal core model
- Prospects of subcritical molten salt reactor for minor actinides incineration in closed fuel cycle
- Usage of burnt fuel isotopic compositions from engineering codes in Monte-Carlo code calculations
- Neutron-kinetic and thermo-hydraulic uncertainties in the study of Kalinin-3 benchmark
- Inter-assembly gap deviations in VVER-1000: Accounting for effects on engineering margin factors
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2014
- Technical Contributions/Fachbeiträge
- Assessment of the uncertainties of MULTICELL calculations by the OECD NEA UAM PWR pin cell burnup benchmark
- Development of codes and KASKAD complex
- Applying full multigroup cell characteristics from MCU code to finite difference calculations of neutron field in VVER core
- Calculations of 3D full-scale VVER fuel assembly and core models using MCU and BIPR-7A codes
- An analysis of reactivity prediction during the reactor start-up process
- Experimental and computational investigations of heat and mass transfer of intensifier grids
- Implementation of CFD module in the KORSAR thermal-hydraulic system code
- Numerical and experimental investigation of 3D coolant temperature distribution in the hot legs of primary circuit of reactor plant with WWER-1000
- Analyses of Beyond Design Basis Accident Homogeneous Boron Dilution Scenarios
- Analysis of heterogeneous boron dilution transients during outages with APROS 3D nodal core model
- Prospects of subcritical molten salt reactor for minor actinides incineration in closed fuel cycle
- Usage of burnt fuel isotopic compositions from engineering codes in Monte-Carlo code calculations
- Neutron-kinetic and thermo-hydraulic uncertainties in the study of Kalinin-3 benchmark
- Inter-assembly gap deviations in VVER-1000: Accounting for effects on engineering margin factors
