Transient thermal-hydraulic analysis for reactor cores
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7136135
- Rand Corp., Santa Monica, CA
None
- OSTI ID:
- 7136135
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor core transient analysis using coupled neutronics and thermal-hydraulic models
CORTRAN code for whole-core LMFBR transient thermal-hydraulic analysis
Whole-core thermal-hydraulic transient code development and verification for LMFBR analysis
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6870751
CORTRAN code for whole-core LMFBR transient thermal-hydraulic analysis
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5715456
Whole-core thermal-hydraulic transient code development and verification for LMFBR analysis
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5715463
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
COOLING SYSTEMS
FLUID FLOW
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
THERMODYNAMICS
TRANSIENTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
COOLING SYSTEMS
FLUID FLOW
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
THERMODYNAMICS
TRANSIENTS