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Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5

Stefanova, Antoaneta ; Groudev, Pavlin; Sanchez-Espinoza, Victor Hugo ORCID iD icon 1; Zavala, Gianfranco Huaccho 1
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

This paper presents a comparative analysis of the Main Steam Line Break (MSLB) in a VVER-1000 reactor
simulated with RELAP5 using Point Kinetics and the coupled code TRACE5-P05/PARCS using 3D kinetics. In the
MSLB-scenario, it is assumed that the main steam line break of 580 mm inner diameter is located between the
steam generator (SG) and the steam isolation valve (SIV), outside the containment. In a MSLB, a non-symmetric
overcooling of the primary coolant takes place leading to a positive reactivity insertion. Hence, the main safety
concern is to assess if the core may become critical despite SCRAM and it there is a considerable power increase
(return-to-power). This paper will discuss the capabilities of different computational approaches to simulate the
VVER-1000 plant behaviour during a MSLB; one approach based on 1D thermal hydraulics and Point Kinetics
while the other one based on 3D thermal hydraulics of the reactor pressure vessel (RPV) and 1D thermal hy-
draulics for the remaining plant components based on a 3D neutron kinetics model. The analyses are performed
for Beginning of Cycle (BOC) conditions i.e., with a fresh core loading when the plant is operated at nominal
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Verlagsausgabe §
DOI: 10.5445/IR/1000170267
Veröffentlicht am 26.04.2024
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 08.2024
Sprache Englisch
Identifikator ISSN: 0306-4549, 1873-2100
KITopen-ID: 1000170267
Erschienen in Annals of Nuclear Energy
Verlag Elsevier
Band 203
Seiten Art.-Nr.: 110518
Nachgewiesen in Dimensions
Scopus
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