ANALYSES OF TRANSIENTS IN THE MSRE SYSTEM WITH $sup 233$U FUEL.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-23-037483
- OSTI ID:
- 4765556
- Report Number(s):
- ORNL-4397
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-69
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N38120* -Power Reactor Development-Control Systems
ACCIDENTS
ANALOG SYSTEMS
CONTROL SYSTEMS
MOLTEN SALT REACTORS
MSRE
POWER
REACTIVITY
SIMULATORS
STABILITY
STARTUP
TRANSIENTS
URANIUM 233
MOLTEN SALT REACTOR EXPERIMENT/transients in uranium- 233 fueled
adequacy of control and safety systems during
REACTOR SIMULATORS/ transient analysis in uranium-233 fueled MSRE with analog
ACCIDENTS
ANALOG SYSTEMS
CONTROL SYSTEMS
MOLTEN SALT REACTORS
MSRE
POWER
REACTIVITY
SIMULATORS
STABILITY
STARTUP
TRANSIENTS
URANIUM 233
MOLTEN SALT REACTOR EXPERIMENT/transients in uranium- 233 fueled
adequacy of control and safety systems during
REACTOR SIMULATORS/ transient analysis in uranium-233 fueled MSRE with analog