New models in VERONA 7.0 system
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István Pós
Abstract
Nowadays the installation of a new modernized VERONA core monitoring system (version V7.0) is in process at the NPP Paks. The most important steps of the current improvements are as follows: complete replacement of the hardware and the local area network; application of a new operating system and “virtual machine” (VM) technology; implementation of a new human-system interface; and last but not least, introduction of improved reactor physics calculations. Basic novelty of the modernized core analysis is the application of general purpose graphical processing units (GPGPU) in the on-line core-follow module. This new technology has allowed of performing the real-time node-wise core analysis by standard Paks NPP core design codes HELIOS/C-PORCA. The present paper gives a brief overview of the system version (V7.0), focusing to the models of reactor physics and results of validation. Main characteristics of new approaches of the modified on-line reactor physics calculations are also described.
Kurzfassung
Derzeit wird das modernisierte VERONA-Kernmonitoringsystem VERONA V7.0 im KKW-Paks installiert. Die wichtigsten Verbesserungen sind der komplette Hardwareautausch und der lokalen Netzwerks, die Anwendung eines neuen Betriebssystems und der Virtual-Machine-Technology, die Erstellung neuer Eingabemasken und die verbesserte Berechnung der Reaktorphysik. So setzt die Kernüberwachung nun auf graphische Prozessoreinheiten auf und erlaubt die real-time Kern-Berechnung einzelner Nodes mit Hilfe der Standard-Nodalisierung des Kerns des KKW-Paks mit dem Programm HELIOS/C-PORCA. Im Beitrag wird die aktuelle Version 7.0 kurz vorgestellt mit dem Fokus auf die Modellierung der Reaktorphysik und der Validierung der Ergebnisse.
References
1 Végh, J.; et al.: Core Analysis at Paks NPP with a New Generation of VERONA. Nuclear Engineering and Design238 (2008) 1316–133110.1016/j.nucengdes.2007.10.013Search in Google Scholar
2 Végh, J.; et al.: VERONA V6.22 – an Enhanced Reactor Analysis Tool Applied for Continuous Core Parameter Monitoring at Paks NPP. Nuclear Engineering and Design292 (2015) 261–27610.1016/j.nucengdes.2015.06.006Search in Google Scholar
3 Pós, I.; Parkó, T.; Patai, Sz.: Application of Discontinuity Factors in C-PORCA 7 Code. Proc. of the 20th Symposium of AER, Hanasaari, Finland, 20–24 September, 2010Search in Google Scholar
4 Casal, J. J.; et al.: HELIOS: Geometric Capabilities of a New Fuel-assembly Program. Proc. of the International Topical Meeting Advances in Mathematics, Computations and Reactor Physics, 1991., Pittsburgh, USASearch in Google Scholar
5 Pós, I.: Application of GPT for Reconstruction of Assembly-wise Power Distribution. Proc. of the 4th Symposium of AER, Sozopol, Bulgaria, October 1994Search in Google Scholar
6 Lewis, E. E.: Primal, Mixed and Hybrid Finite Elements For Neutronics Computations M&C, Madrid, Spain, 1999Search in Google Scholar
7 Csom, Gy.; et al.: Calculation of Spatial Weight Functions for VVER-440 Ex-Core Neutron Detectors. Eleven Symposium of AER 2001Search in Google Scholar
8 Henry, A. F.: The Application of reactor Kinetics to the Analysis of Experiments. Nuclear Science and Engineering3 (1958) 52–7010.13182/NSE58-1Search in Google Scholar
© 2016, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2015
- Technical Contributions/Fachbeiträge
- Monte-Carlo code calculation of 3D reactor core model with usage of burnt fuel isotopic compositions, obtained by engineering codes
- Xenon instability study of large core Monte Carlo calculations
- Error detection in core loading in the condition of asymmetrical distribution of power
- New models in VERONA 7.0 system
- Methodology for determining of the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations
- Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents
- Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop
- Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
- Coupled code analysis of uncertainty and sensitivity of Kalinin-3 benchmark
- Efficient introduction of natural uranium and thorium into nuclear energy system
- Economical aspects of multiple plutonium and uranium recycling in VVER reactors
- Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO
- Uncertainty analysis and flow measurements in an experimental mock-up of a molten salt reactor concept
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2015
- Technical Contributions/Fachbeiträge
- Monte-Carlo code calculation of 3D reactor core model with usage of burnt fuel isotopic compositions, obtained by engineering codes
- Xenon instability study of large core Monte Carlo calculations
- Error detection in core loading in the condition of asymmetrical distribution of power
- New models in VERONA 7.0 system
- Methodology for determining of the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations
- Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents
- Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop
- Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
- Coupled code analysis of uncertainty and sensitivity of Kalinin-3 benchmark
- Efficient introduction of natural uranium and thorium into nuclear energy system
- Economical aspects of multiple plutonium and uranium recycling in VVER reactors
- Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO
- Uncertainty analysis and flow measurements in an experimental mock-up of a molten salt reactor concept
