Simulation of the hydrogen distribution in the confinement of the Ignalina nuclear power plant
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E. Babilas
Abstract
The Accident Localisation System (ALS) of the Ignalina nuclear power plant is a “pressure suppression” type confinement, which protects the population, workers and environment from radiation hazards. According to the safety justification of RBMK-1500 reactors, ∼110 m3 of hydrogen is released to the ALS compartments during a maximum design basis accident. To prevent the possible hydrogen accumulation and combustion, a hydrogen concentration control system is installed. The main goal of the present paper is to present the ALS model for the COCOSYS code and assess the effectiveness of the hydrogen control system of the Ignalina nuclear power plant. The analysis performed identified locations of possible hydrogen accumulation in the ALS compartments during the transient processes and assessed the mixture combustibility in these locations for a maximum design basis accident scenario.
Kurzfassung
Das Störfallbegrenzungssystem (ALS) des Kernkraftwerks in Ignalina ist ein Druckabbausystem zum Schutz der Bevölkerung, des Personals und der Umgebung. Bei dem schwersten Auslegungsstörfall werden entsprechend der Sicherheitsbewertungen der RBMK-1500 Reaktoren ca. 110 m3 Wasserstoff in das Confinement freigesetzt. Zur Verhinderung von Wasserstoffansammlung und -verbrennung wurde ein Wasserstoffüberwachungssystem installiert. Der Beitrag beschreibt die Modellierung des Störfallbegrenzungssystems für den COCSYS-Code und die Bewertung der Wirksamkeit des Wasserstoffüberwachungssystems im Kernkraftwerk Ignalina. Es wurden die Möglichkeiten lokaler Wasserstoffanreicherungen im Confinement bei Transientenverläufen untersucht und die dort unter Bedingungen des schwersten Auslegungsstörfalls entstehenden Brenngemische bewertet.
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
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- On the plane-wave theory in fertile uranium
- Safety and security of radioactive sources – international provisions
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- 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