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Approach to accident management in RBMK-1500
Authors:A Kaliatka  E Urbonavicius  E Uspuras
Affiliation:aLithuanian Energy Institute, Breslaujos g. 3, LT-44403 Kaunas, Lithuania
Abstract:In order to ensure the safe operation of the nuclear power plants accident management programs are being developed around the world. These accident management programs cover the whole spectrum of accidents, including severe accidents. A lot of work is done to investigate the severe accident phenomena and implement severe accident management in NPPs with vessel-type reactors, while less attention is paid to channel-type reactors CANDU and RBMK.Ignalina NPP with RBMK-1500 reactor has implemented symptom based emergency operation procedures, which cover management of accidents until the core damage and do not extend to core damage region. In order to ensure coverage of the whole spectrum of accidents and meet the requirements of IAEA the severe accident management guidelines have to be developed.This paper presents the basic principles and approach to management of beyond design basis accidents at Ignalina NPP. In general, this approach could be applied to NPPs with RBMK-1000 reactors that are available in Russia, but the design differences should be taken into account.
Keywords:AFWP  auxiliary feedwater pump  ALS  accident localisation system  BDBA  beyond design basis accident  BRU-B  Valve for steam discharge to ALS (Russian abbreviation)  BSRC  bottom steam reception chamber  BWR  boiling water reactor  CTCS  condenser tray cooling system  ECCS  emergency core cooling system  EOP  emergency operating procedure  FP  fission products  GDH  group distribution header  HCC  hot condensate chamber  IAEA  International Atomic Energy Agency  LOCA  loss-of-coolant accident  LWP  lower water piping  LWR  light water reactor  MCC  main cooling circuit  MCP  main cooling pump  MFWP  main feedwater pump  MSV  main safety valve  NPP  nuclear power plant  PPB  reinforced leaktight compartments (Russian abbreviation)  PWR  pressurised water reactor  PSA  probabilistic safety analysis  RCS  reactor cooling system  SAMG  severe accident management guidelines  SRV  steam relief valve  TSC  Technical Support Centre  VVER  water-water energy reactor (Russian abbreviation)  WOG  Westinghouse Owners Group
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