Best estimate analysis of group distribution header blockage events in RBMK-1500 reactors
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A. Kaliatka
Abstract
The analysis of Group Distribution Header (GDH) blockage events shows that the integrity of several fuel channels could be violated. A best estimate analysis of GDH blockage events in the RBMK-1500 reactor (Large Channel Type Water-cooled Graphite-moderated Reactor) of the Ignalina Nuclear Power Plant is performed. Uncertainties of the initial and boundary conditions as well as ATHLET code models were taken into account during the simulation. The analysis is performed employing the code ATHLET Mod. 1.2 Cycle D and the package SUSA 3.5. In this paper the ATHLET code model of Ignalina NPP, event scenarios and results of the analysis are presented. Analysis results show that GDH blockage events do not lead to severe consequences.
Kurzfassung
Die Untersuchung der Verstopfung des Verteilers hat gezeigt, dass die Integrität einiger Druckröhren gefährdet sein könnte. Es wurden Best-Estimate-Analysen der Verstopfung der Verteiler des RBMK-1500 (Graphit-moderierter Siedewasser-Druckröhrenreaktor) des Kernkraftwerks Ignalina durchgeführt. Die Unsicherheiten sowohl der getroffenen Annahmen als auch des ATHLET Codes wurden bei der Simulation berücksichtigt. Die Analyse wurde mit dem ATHLET Code Mod. 1.2 Cycle D und dem Programm SUSA 3.5 vorgenommen. In diesem Beitrag wird die ATHLET Code Modellierung für das Kernkraftwerk Ignalina sowie der Ereignisverlauf und die Untersuchungsergebnisse dargestellt. Die Ergebnisse zeigen, dass eine Verstopfung des Verteilers keine schweren Konsequenzen nach sich zieht.
References
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© 2005, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
- Integrated management systems in the nuclear field
- Phenomenological model for non-equilibrium deuteron emission in nucleon induced reactions
- Best estimate analysis of group distribution header blockage events in RBMK-1500 reactors
- Simulation of the hydrogen distribution in the confinement of the Ignalina nuclear power plant
- Neutronic calculations for the new fuel configuration of the ETRR-1 research reactor
- Design stability and safety margins of the ETRR-2 core cooling system regarding seismic loads
- Thermal-hydraulic assessment of topaz irradiation processes at the ETRR-2 research reactor
- The HN method for slab albedo problem for linearly anisotropic scattering
- On the plane-wave theory in fertile uranium
- Safety and security of radioactive sources – international provisions
- The singular eigenfunction method: the critical slab problem for linearly anisotropic scattering
- Technical Notes/Technische Mitteilungen
- Results of in vitro intercomparison tests of the Coordinating Office on Incorporation Monitoring in Germany
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Technical Contributions/Fachbeiträge
- Integrated management systems in the nuclear field
- Phenomenological model for non-equilibrium deuteron emission in nucleon induced reactions
- Best estimate analysis of group distribution header blockage events in RBMK-1500 reactors
- Simulation of the hydrogen distribution in the confinement of the Ignalina nuclear power plant
- Neutronic calculations for the new fuel configuration of the ETRR-1 research reactor
- Design stability and safety margins of the ETRR-2 core cooling system regarding seismic loads
- Thermal-hydraulic assessment of topaz irradiation processes at the ETRR-2 research reactor
- The HN method for slab albedo problem for linearly anisotropic scattering
- On the plane-wave theory in fertile uranium
- Safety and security of radioactive sources – international provisions
- The singular eigenfunction method: the critical slab problem for linearly anisotropic scattering
- Technical Notes/Technische Mitteilungen
- Results of in vitro intercomparison tests of the Coordinating Office on Incorporation Monitoring in Germany
