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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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