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Title: An examination of the accident scenario in the Chernobyl Nuclear Power Station

Journal Article · · Nucl. Saf.; (United States)
OSTI ID:5688481
; ; ; ;

The accident scenario in the Chernobyl Nuclear Power Station was examined by using EUREKA-2 analyses and the experimental results from the Nuclear Safety Research Reactor. The accident scenario is characterized by two power excursions, pressure tubes bursting from rapid steam generation resulting from molten fuel dispersion into the coolant, heatup caused by zirconium-water or zirconium-air reaction and subsequent burning of graphite rings, and a graphite moderator fire. These events can be explained quantitatively without conflict with the report submitted by the USSR State Committee to the International Atomic Energy Agency Experts' Meeting in August 1986.

Research Organization:
Japan Atomic Energy Research Institute, Tokai, Ibaraki; Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki, Japan
OSTI ID:
5688481
Journal Information:
Nucl. Saf.; (United States), Vol. 28:4
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CHERNOBYLSK-4 REACTOR
FUEL-CLADDING INTERACTIONS
FUEL-COOLANT INTERACTIONS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
CHEMICAL REACTION KINETICS
E CODES
EXPLOSIONS
FIRES
FUEL RODS
GRAPHITE
HEAT TRANSFER
HYDRAULICS
HYDROGEN
NIOBIUM
PRESSURE TUBES
RUPTURES
TRANSIENTS
ZIRCONIUM
ACCIDENTS
CARBON
COMPUTER CODES
COOLING SYSTEMS
ELEMENTAL MINERALS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
FUEL ELEMENTS
GRAPHITE MODERATED REACTORS
KINETICS
LWGR TYPE REACTORS
MECHANICS
METALS
MINERALS
NONMETALS
POWER REACTORS
REACTION KINETICS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL REACTORS
TRANSITION ELEMENTS
TUBES
WATER COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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