Severe fuel damage scoping test performance
Journal Article
·
· AIChE Symp. Ser.; (United States)
OSTI ID:5375866
As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. The first test of Phase I of this series has been successfully completed in the Power Burst Facility at the Idaho National Engineering Laboratory. Following the first test, calculations were performed using the TRAC-BD1 computer code with actual experimental boundary conditions. This paper discusses the test conduct and performance and presents the calculated and measured test bundle results. The test resulted in a slow heatup to 2000 K over about 4 h, with an accelerated reaction of the zirconium cladding at temperatures above 1600 K in the lower part of the bundle and 2000 K in the upper portion of the bundle.
- Research Organization:
- EG and G Idaho, Inc., P.O. Box 1625, Idaho Falls, ID
- OSTI ID:
- 5375866
- Journal Information:
- AIChE Symp. Ser.; (United States), Journal Name: AIChE Symp. Ser.; (United States) Vol. 79:225; ISSN ACSSC
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOUNDARY CONDITIONS
CLADDING
COMPUTER CALCULATIONS
COMPUTER CODES
DEPOSITION
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUELS
MATERIALS
METALS
NUCLEAR FUELS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SURFACE COATING
T CODES
TESTING
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOUNDARY CONDITIONS
CLADDING
COMPUTER CALCULATIONS
COMPUTER CODES
DEPOSITION
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUELS
MATERIALS
METALS
NUCLEAR FUELS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SURFACE COATING
T CODES
TESTING
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM