TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR
An analysis of the transient behavior of a 255-Mw(e) advanced sodium graphite reactor, previously described in NAA-SR-3829, is presented. The reactor and its components are briefly described. Nuclear and thermal characteristics are presented as far as they affect reactor kinetics or are essential in interpreting the results. The study includes an investigation of the inherent kinetic characteristics of the reactor, as well as and analysis of its transient behavior for all conceivable conditions of abnormal operations. Assumed reactor excursions are analyzed with and without ensuing protective system action. It is shown that the reactor is dynamically stable and that power transients which are followed by normal protective system actions will not lead to potentially unsafe conditions. The conclusion is reached furthermore, that uncontrolled rod withdrawal accidents from source power will be terminated by coolant choking'' and fuel meltdown before extensive coolant boiling occurs, and that the large thermal capacity and long-time constant of the upper plenum will provide protection against pool boiling for other less serious accidents until the reactor can be shut down by external means. (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-16-004971
- OSTI ID:
- 4823381
- Report Number(s):
- NAA-SR-3829(Suppl.1)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ACCIDENTS
BOILING
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
DELAYED NEUTRONS
EXCURSIONS
FAILURES
FUEL ELEMENTS
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
LIQUID METAL COOLANT
MELTING
NEUTRON FLUX
PLANNING
POWER PLANTS
PROMPT NEUTRONS
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RODS
SHUTDOWN
SODIUM
SPECIFIC HEAT
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
BOILING
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
DELAYED NEUTRONS
EXCURSIONS
FAILURES
FUEL ELEMENTS
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
LIQUID METAL COOLANT
MELTING
NEUTRON FLUX
PLANNING
POWER PLANTS
PROMPT NEUTRONS
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RODS
SHUTDOWN
SODIUM
SPECIFIC HEAT
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS