Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
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M. Iqbal
Abstract
A closed loop auto control system has been developed and implemented at the Pakistan Research Reactor-2 (PARR-2). For interfacing of the site signals with a computer, a data acquisition card was employed. The system utilizes nine signals and, on their basis, carries out continuous on-line analysis, maintaining safe operation. On-line reactivity measurement is included in this software. Also, it generates control signals for keeping the reactor at the desired power level in auto-mode round-the-clock without human intervention. In case of abnormal conditions for either power or temperature or radiation level, alarms are initiated and if their levels reach beyond prescribed safe operation regime, automatic shutdown sequence is initiated. The control system has been thoroughly tested for various postulated scenarios. The test results have been in good agreement with the expected response.
Kurzfassung
Für den Pakistanischen Forschungsreaktor (PARR-2) des Typs Miniature Neutron Source Reactor (MNSR) wurde eine automatische Steuerungssoftware entwickelt und installiert. Dazu wurde das bestehende Steuerungssystem über eine Datenerfassungskarte mit der neuen Software, die auf einem separaten Computer installiert wurde, verbunden. Neun Betriebssignale werden für eine kontinuierliche Onlineanalyse verarbeitet und zur Unterstützung der Aufrechterhaltung des sicheren Betriebs verwendet. Des Weiteren bestimmt die Software Kontrollsignale, um den Reaktor automatisch auf einem vorgegebenen Leistungslevel zu fahren, ohne dass ein Eingreifen des Betriebspersonals notwendig wird. Beim Auftreten von Abweichungen bei den Parametern Leistung, Temperatur oder Strahlungslevel werden Alarme generiert und beim Überschreiten vorher definierter sicherer Betriebsbereiche wird der Forschungsreaktor automatisch abgeschaltet. Die Steuerungssoftware wurde gründlich getestet bei verschiedenen Szenarien und führte dabei zu guten Ergebnissen im Vergleich zum erwarteten Verhalten.
References
1 Ruan, D.; ven der Wal, A. J.: Controlling the power output of a nuclear reactor with fuzzy logic. Info. Sci.110 (1998) 151–177Search in Google Scholar
2 Kim, D. Y.; Seong, P. H.: Fuzzy gain scheduling of velocity PI controller with intelligent learning algorithm for reactor control. Ann. Nucl. Energy24 (1996) 819–827Search in Google Scholar
3 Bock, H. W.; Graf, A.: Reliability aspect of computer-based safety systems for nuclear power plants. Fuel & Energy Abs.37 (1996) 105Search in Google Scholar
4 An, Z.; Liu, L.; Chen, Y.: Design of power auto-regulating system's high reliability controller for 200 MW nuclear eating reactor. Nucl. Power Eng.17 (1996) 299–303Search in Google Scholar
5 Zhao, F.; Cheung, K. C.; Yeung, R. M. K.: Optimal power control system of a research nuclear reactor. Nucl. Eng. and Design219 (2002) 247–25210.1016/S0029-5493(02)00233-9Search in Google Scholar
6 Arab-Alibeik, H.; Setayeshi, S.: An adaptive-cost-function optimal controller design for a PWR nuclear reactor. Ann. Nucl. Energy30 (2003) 739–754Search in Google Scholar
7 Hainoun, A.; Khamiz, I.; Saba, G.: Dynamic analysis of the closed-loop transfer function in the miniature neutron source reactor (MNSR). Nucl. Eng. & Desig.232 (2004) 19–28Search in Google Scholar
8 Qazi, M. K.; Israr, M.; Karim, A.: Revised final safety analysis report on Pakistan Research Reactor-2. PINSTECH, 1994Search in Google Scholar
9 Iqbal, M.; Abdullah, M.; Pervez, S.: Parametric Tests and Measurements after Shimming of Beryllium Reflector in Miniature Neutron Source Reactor (MNSR). Ann. Nucl. Energy29 (2002) 1609–1624Search in Google Scholar
10 A User's manual: The Computer Closed Loop Control System. Institute of Atomic Energy, China, 1989Search in Google Scholar
11 Lamarch, J.: Introduction to Nuclear Reactor Engineering. Adison-Wesely Publishing company, USA, 1977Search in Google Scholar
12 Steffen, G.: A portable digital reactivity meter for power reactors. Kerntechnik19 (1977) 327Search in Google Scholar
© 2009, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)
- Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes
- CFD modelling of insulation debris transport phenomena in water flow
- Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
- Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history
- Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
- Numerical simulation of passive catalytic recombiner
- Some affine solutions for CANDLE burn-up waves in 1D-geometry
- Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants
- Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion
- Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem
- A model for calculation of forward isotropic scattering with application to transport equation in slab geometry
- Training and retraining programme for research reactor operating personnel
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)
- Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes
- CFD modelling of insulation debris transport phenomena in water flow
- Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
- Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history
- Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
- Numerical simulation of passive catalytic recombiner
- Some affine solutions for CANDLE burn-up waves in 1D-geometry
- Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants
- Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion
- Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem
- A model for calculation of forward isotropic scattering with application to transport equation in slab geometry
- Training and retraining programme for research reactor operating personnel
