Results of blind predictions of HDR steam blowdown experiments using the CONTAIN code
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5262417
None
- Research Organization:
- Sandia National Laboratories P.O. Box 5800 Albuquerque, NM 87185
- OSTI ID:
- 5262417
- Report Number(s):
- CONF-831047-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 45
- Country of Publication:
- United States
- Language:
- English
Similar Records
HDR blowdown experiment: A hydraulic/structural prediction
Results of HDR valve experiments and of calculations with the DAPSY code
Comparison of an analytical model with containment blowdown experiments
Conference
·
Sat Oct 01 00:00:00 EDT 1983
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5227279
Results of HDR valve experiments and of calculations with the DAPSY code
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6214437
Comparison of an analytical model with containment blowdown experiments
Conference
·
Wed Jun 01 00:00:00 EDT 1977
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7309455
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACCURACY
BLOWDOWN
BUILDINGS
BWR TYPE REACTORS
C CODES
COMPUTER CODES
CONTAINMENT
CONTAINMENT BUILDINGS
DECOMMISSIONING
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GERMAN FR ORGANIZATIONS
HDR REACTOR
HEAT SINKS
KERNFORSCHUNGSZENTRUM KARLSRUHE
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
PRESSURE MEASUREMENT
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SENSITIVITY ANALYSIS
SINKS
STEAM
TEMPERATURE MEASUREMENT
THERMAL REACTORS
THERMODYNAMICS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACCURACY
BLOWDOWN
BUILDINGS
BWR TYPE REACTORS
C CODES
COMPUTER CODES
CONTAINMENT
CONTAINMENT BUILDINGS
DECOMMISSIONING
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GERMAN FR ORGANIZATIONS
HDR REACTOR
HEAT SINKS
KERNFORSCHUNGSZENTRUM KARLSRUHE
LOSS OF COOLANT
NATIONAL ORGANIZATIONS
PRESSURE MEASUREMENT
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SENSITIVITY ANALYSIS
SINKS
STEAM
TEMPERATURE MEASUREMENT
THERMAL REACTORS
THERMODYNAMICS
WATER COOLED REACTORS
WATER MODERATED REACTORS