The studies of RBMK-1500 reactor core behavior during abnormal operation transients
2004 (English)In: Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, 2004, 1035-1047 p.Conference paper (Refereed)
This paper describes series of RBMK-1500 reactor transient investigations, performed with CORETRAN code. Aspects of the reactor core neutronic and thermal hydraulic behavior during postulated core transients were analyzed, hi particular, RBMK-1500 transients leading to changes in reactor power and core reactivity were considered. Three reactivity-initiated accident cases were addressed: a) spontaneous control rod bank withdrawal in the central part of the core; b) spontaneous control rod bank withdrawal in core periphery and c) release of one Shortened Absorber Rod from the reactor core. Reactor nominal power operation was used as the reference core state. Analysis was performed using data, obtained from the actual plant database recorded for Ignalina Nuclear Power Plant Unit 2 on 27th January 2001. The CORETRAN calculations were benchmarked against STEPAN code results.
Place, publisher, year, edition, pages
2004. 1035-1047 p.
Abnormal operational transients, Control rods, RBMK-1500, Reactivity-initiated accidents, Reactor core analysis
IdentifiersURN: urn:nbn:se:kth:diva-92653ScopusID: 2-s2.0-22344433380ISBN: 0894486837OAI: oai:DiVA.org:kth-92653DiVA: diva2:514182
PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments; Chicago, IL; 25 April 2004 through 29 April 2004
QC 201208162012-04-052012-04-052012-08-16Bibliographically approved