Comparison of ICECO code predictions with COVA experimental data. [LMFBR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5686709
None
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5686709
- Report Number(s):
- CONF-790602-(Summ.)
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 32
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of experimental data with ICECO predictions for an excursion model of a fast breeder reactor
Comparison of computer code predictions with COVA experiments. [LMFBR]
Comparison of ICECO predictions of wave propagation in the rigid two-dimensional vessel experiments
Conference
·
Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7135728
Comparison of computer code predictions with COVA experiments. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5356043
Comparison of ICECO predictions of wave propagation in the rigid two-dimensional vessel experiments
Conference
·
Thu Jun 01 00:00:00 EDT 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7038138
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
STRESS ANALYSIS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
STRESS ANALYSIS