Abstract
The fire hazard analysis methodology and main results of Ignalina Nuclear Power Plant RBMK-1500 type reactor's systems and rooms with safety elements and also rooms adjacent to main rooms and other fire hazardous rooms are presented. In total this concerns about 2100 rooms in the control area of one Unit, where the fire could influence nuclear safety of the power plant. For this purpose the decision-making computerized system FIRE-INPP was developed. It includes modules for recording necessary information, data processing, analysis and assessment on compliance of rooms at Ignalina NPP with national fire safety requirements and international recommendations regarding fire hazard. Screening algorithms and decision-making module are the basis for the decision-making computerized system, that allows to perform unambiguous, reliable and fast fire hazard analysis and give recommendations to ensure fire safety adequacy.
Kurzfassung
Die Methodik der Brandgefahrenanalyse und die wesentlichen Ergebnisse für die Ignalina Kernkraftwerk RBMK-1500-Typ-Reaktorsysteme und Räume mit Sicherheitseinrichtungen sowie angrenzende Räume und andere brandschutztechnisch relevante Räume werden vorgestellt. Insgesamt betrifft das ungefähr 2100 Räume im Kontrollbereich eines Blocks, in denen das Feuer die kerntechnische Sicherheit des Kraftwerks beeinflussen könnte. Dazu wurde das Rechenprogramm FIRE-INPP entwickelt, das die Entscheidungfindung unterstützen soll. Das Programm schließt Module ein, um notwendige Informationen, Datenverarbeitung, Analyse und die Bewertung von Räumen des Ignalina-Kernkraftwerks hinsichtlich der Einhaltung von nationalen Brandschutzanforderungen und internationalen Empfehlungen zu überprüfen. Die Algorithmen zur Raumauswahl und das Modul zur Unterstützung der Entscheidungsfindung ist die Basis für das Rechenprogramm das es erlaubt, eine eindeutige, zuverlässige und schnelle Brandgefahrenanalyse durchzuführen und Empfehlungen zu geben, um eine angemessene Brandschutzsicherheit sicher zu stellen.
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