Chernobyl accident sequence
Journal Article
·
· Nucl. Saf.; (United States)
OSTI ID:6206817
A historic meeting was held Aug. 25-29, 1986, in Vienna, Austria. A delegation of U.S.S.R. experts presented detailed information on the design characteristics of the RBMK-1000 type of reactor and their evaluation of all aspects of the Chernobyl accident, including causes, events, measured releases, mitigation efforts, response measures taken, atmospheric transport, and the consequences. This article was developed as a result of the authors' participation in this meeting and participation in additional one-on-one interactions with the U.S.S.R. experts. An overview is presented of the important design features, the ill-fated experiment, and the significant events up to the time of the initial excursion.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 6206817
- Journal Information:
- Nucl. Saf.; (United States), Vol. 28:1
- 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
REACTOR ACCIDENTS
DESIGN
EMERGENCY PLANS
ERRORS
EXPLOSIONS
FIRES
HUMAN FACTORS
IAEA
MAN-MACHINE SYSTEMS
MITIGATION
PRIMARY COOLANT CIRCUITS
RADIATION DOSES
RADIATION HAZARDS
REACTIVITY INSERTIONS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR MAINTENANCE
REACTOR OPERATORS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR SHUTDOWN
SPECIFICATIONS
USSR
ACCIDENTS
ASIA
CONTROL SYSTEMS
COOLING SYSTEMS
DOSES
EASTERN EUROPE
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
EUROPE
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
INTERNATIONAL ORGANIZATIONS
LWGR TYPE REACTORS
MAINTENANCE
PERSONNEL
POWER REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SHUTDOWNS
THERMAL REACTORS
WATER COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CHERNOBYLSK-4 REACTOR
REACTOR ACCIDENTS
DESIGN
EMERGENCY PLANS
ERRORS
EXPLOSIONS
FIRES
HUMAN FACTORS
IAEA
MAN-MACHINE SYSTEMS
MITIGATION
PRIMARY COOLANT CIRCUITS
RADIATION DOSES
RADIATION HAZARDS
REACTIVITY INSERTIONS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR MAINTENANCE
REACTOR OPERATORS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR SHUTDOWN
SPECIFICATIONS
USSR
ACCIDENTS
ASIA
CONTROL SYSTEMS
COOLING SYSTEMS
DOSES
EASTERN EUROPE
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
EUROPE
GRAPHITE MODERATED REACTORS
HAZARDS
HEALTH HAZARDS
INTERNATIONAL ORGANIZATIONS
LWGR TYPE REACTORS
MAINTENANCE
PERSONNEL
POWER REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SHUTDOWNS
THERMAL REACTORS
WATER COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated