Approach to accident management in RBMK-1500 |
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Authors: | A. Kaliatka E. Urbonavicius E. Uspuras |
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Affiliation: | aLithuanian Energy Institute, Breslaujos g. 3, LT-44403 Kaunas, Lithuania |
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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. |
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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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