Analysis of a steam generator tube rupture under realistic initial and boundary conditions
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Abstract
Within the framework of safety analysis the TÜV NORD SysTec GmbH & Co. KG has analyzed a steam generator tube rupture for a pressurized water reactor under realistic initial and boundary conditions. During the accident an undesirable backing of the coolant pressure by switching-on the safety injection pumps is avoided, which can endanger the coolant retention in the steam generators, because the shut off heads of the safety injection pumps are larger than the response pressure of the safety valves.
Kurzfassung
Die TÜV NORD SysTec GmbH & Co. KG hat im Rahmen einer Sicherheitsanalyse das Anlagenverhalten bei einem Dampferzeugerheizrohrleck eines Druckwasserreaktors unter Verwendung realistischer Anfangs- und Randbedingungen analysiert. Während dieses Störfalls werden die Sicherheitseinspeisepumpen nicht zugeschaltet. Folglich bleiben die Sicherheitsventile der Dampferzeuger geschlossen. Das auf die Sekundärseite übergetretene Kühlmittel wird hier zurückgehalten.
© 2009, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- AVR prototype pebble bed reactor: a safety re-evaluation of its operation and consequences for future reactors
- Design Concept of the High Performance Light Water Reactor
- Behavior of CANDU fuel under power pulse conditions at the TRIGA reactor of INR Pitesti
- Plate heat exchanger – inertia flywheel performance in loss of flow transient
- Performance analyses of the communication networks of a modern supervision and control system of research reactors
- Thermal analytical model for MoO3 ampoules irradiated in a high neutron flux
- Effect of using various grades of plutonium in the protective liquid wall of an IFE type fusion reactor
- A discrete ordinates scheme for void fraction evaluation with nonstandard reflective conditions and weakly divergent beams
- Application of the Laplace transform method for the albedo boundary conditions in multigroup neutron diffusion eigenvalue problems in slab geometry
- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
- Optimizing the dynamic response of the H. B. Robinson nuclear plant using multiobjective particle swarm optimization
- Assessment for inside building dispersion of aerosol from an outdoor radiological release
- Technical Notes/Technische Mitteilungen
- Analysis of a steam generator tube rupture under realistic initial and boundary conditions
