Development of codes and KASKAD complex
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M. P. Lizorkin
Abstract
A brief description of the development history of engineering computer codes for VVER reactor calculations, which have been developed in the VVER physics department of NRC Kurchatov institute, since the end of 1950 s till now, are given in the report. The modern status of the basic codes of the Kurchatov institute for VVER fuel loadings design and safety analysis (TVS-M, KASKAD-BIPR-PERMAK, BIPR8, PERMAK-3D, SC1, TOPRA, ATHLET/BIPR-VVER, TIGR-1, etc.) is characterized from various points of view. Some specific problems which are shown during designing of fuel cycles, optimisation of fuel and technologies will be commented. They demand decisions within the complex of programs and, accordingly, demand the further development of a complex or working out and inclusion in a complex of new programs.
Kurzfassung
Seit Ende der 50er Jahres des letzten Jahrhunderts werden am Kurchatov-Instititut Programme zur Berechnung von WWER entwickelt. Insbesondere der aktuelle Status der Basisprogramme zur Berechnung von Kernbeladungen und zur Durchführung von Sicherheitsanalysen (wie TVS-M, KASKAD-BIPR-PERMAK, BIPR8, PERMAK-3D, SC1, TOPRA, ATHLET/BIPR-VVER, TIGR-1) wird beschrieben. Dabei werden auch spezielle Anforderungen an die Programme, die aus der Entwicklung von Brennstoffzyklen, der Optimierung der Brennstoffe und der eingesetzten Technologien resultieren, kommentiert. Es wird dargestellt, in welche Richtung die weitere Entwicklung dieser Programme in Zukunft voranschreiten wird.
References
1 Theoretical investigations of the physical properties of VVER-type uranium-water lattices. Final report of TIC. Vol. 2. Budapest 1994Suche in Google Scholar
2 Lizorkin, M. P.; Semenov, V. N.; Ionov, V. S.; Lebedev, V. I.: Time Dependent Spatial Neutron Kinetic Algorithm for BIPR8 and its Verification. Proc. Second Symposium of AER, KFKI Atomic Energy Research Institute, Budapest (1992) 389Suche in Google Scholar
3 Lizorkin, M.; Nikonov, S.; Langenbuch, S.: Velkov, K.: Development and Application of the Coupled Thermal-Hydraulics and Neutron-Kinetics Code ATHLET/BIPR-VVER for Safety Analysis. EUROSAFE-2006, Paris, November 13–14, 2006Suche in Google Scholar
4 Gordienko, P.; et. al.: The recovery procedure of pin-by-pin fields of power distribution in the core of VVER type of reactor for the program BIPR-8. Verification calculations. Proceedings of 22 Symposium AER, October 1–5, Pruhonice, Czech Republic, 2012Suche 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
