BWR severe accident sequence analyses at ORNL - some lessons learned
Conference
·
OSTI ID:5405678
Boiling water reactor severe accident sequence studies are being carried out using Browns Ferry Unit 1 as the model plant. Four accident studies were completed, resulting in recommendations for improvements in system design, emergency procedures, and operator training. Computer code improvements were an important by-product.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5405678
- Report Number(s):
- CONF-8310143-11; ON: DE84001971
- Resource Relation:
- Conference: 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983
- 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
BROWNS FERRY-1 REACTOR
REACTOR ACCIDENTS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
EMERGENCY PLANS
REACTOR OPERATORS
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
ENRICHED URANIUM REACTORS
MIXED SPECTRUM REACTORS
PERSONNEL
POWER REACTORS
REACTORS
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
REACTOR ACCIDENTS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
EMERGENCY PLANS
REACTOR OPERATORS
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
ENRICHED URANIUM REACTORS
MIXED SPECTRUM REACTORS
PERSONNEL
POWER REACTORS
REACTORS
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled