ANALOG STUDY OF THE HNPF PROTECTIVE SYSTEM FOR THE U-Mo CORE

Technical Report · Thu Jul 16 04:00:00 EDT 1959

OSTI ID:4807079

Fletchall, D E

The analog diagrams used in the simulation of the protective system are described. With the reactor operating at full power and flow, control rod withdrawal, loss of coolant flow, and coolant inlet temperature transients were studied. Scrams and setbacks on signals from the powerflow comparator and high outlet coolant temperature circuits were investigated for each transient. Setback hysteresis, thermocouple time constants, and scram and setback setpoints were the parameters studied. Startup transients with setback from the period circuit in the intermediate power range were investigated. Time for setback to occur was the variable parameter for the startup transient. Recommendations are included for further studies to insure protection for thc core against high temperature when operating at reduced power and flow (B.O.G.)

• Research Organization: Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-16-005027
• OSTI ID: 4807079
• Report Number(s): NAA-SR-Memo-4094
• Country of Publication: United States
• Language: English

Related Subjects

ANALOG SYSTEMS
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
COOLANTS
DIAGRAMS
DISTRIBUTION
EFFICIENCY
FAILURES
FLUID FLOW
FUEL ELEMENTS
HIGH TEMPERATURE
HNPF
LEAKS
LOSSES
MOLYBDENUM
MONITORING
NEUTRON FLUX
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REMOTE CONTROL
RODS
SENSITIVITY
SHUTDOWN
SIGNALS
STARTUP
TEMPERATURE
THERMOCOUPLES
TRANSIENTS
URANIUM