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Strength evaluation of a steam distribution device in the Ignalina NPP accident localisation system
Authors:Gintautas Dundulis  Renatas Karalevicius  Sigitas Rimkevicius  Ronald F Kulak  Algirdas H Marchertas
Affiliation:aLaboratory of Nuclear Installation Safety, Lithuanian Energy Institute, 3 Breslaujos, 44403 Kaunas 35, Lithuania;bRFK Engineering Mechanics Consultants, USA;cNorthern Illinois University, USA
Abstract:The Ignalina NPP has a pressure suppression type of confinement, which is referred to as the accident localization system (ALS). The ALS prevents the release of the radioactive material from the NPP to the environment during a loss-of-coolant accident (LOCA). Ten water pools are located in the two ALS towers (five pools in each tower), which separate the dry well from the wet well. These water pools condense the accident-generated steam and prevent high overpressures in the compartments.The steam distribution device (SDD), with the vertical vent pipes (nozzles) that are inserted under the water of the condensing pools, connects the dry well and the wet well. In case of an accident, these components must be capable of withstanding the dynamic loads generated by a LOCA for successful pressure suppression function.This paper presents the transient analysis of the SDD and their connections to the vertical steam corridors following a LOCA. A thermo-hydraulic analysis of the SDD was performed using the state-of-the-art COCOSYS code to determine pressure and temperature histories resulting from a LOCA. The finite element code NEPTUNE was used to evaluate the structural integrity of the SDD and its supporting reinforced concrete wall. Results show that, although portions of the SDD undergo plastic response and the outside surface of the vertical steam corridor reinforced concrete wall cracks, the structural integrity of the SDD and wall are maintained during a LOCA.
Keywords:ALS  accident localization system  BRU-B  valve for steam discharge to ALS tower (Russian abbreviation)  BSRC  bottom steam reception chamber  CTCS  condenser tray cooling circuit  ECCS  emergency core cooling system  GDH  group distribution header  HCC  hot condensate chamber  LOCA  loss-of-coolant accident  MCC  main circulation circuit  MDBA  maximum design basis accident  MSV  main safety valve  NPP  nuclear power plant  RBMK  Russian acronym for ‘channelized large power reactor’  SDD  steam distribution device  SDH  steam distribution header  VATESI  Lithuanian state atomic energy safety inspection
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