ADDENDUM TO D102A HAZARDS REPORT

Technical Report · Wed Apr 15 04:00:00 EST 1959

OSTI ID:4820991

Gamertsfelder, C C; Blumberg, B; Schoenberger, T W

. Further evaluation of the assembly is presented with regard to the hazards involved in the continuation of Heat Transfer Reactor Experiment No. 3. This additional evaluation was made taking into consideration the condttions leading to the power excursion of November 18, 1958. Operation of the rebuilt core is scheduled to start in July of 1959. The reactor is essentially the same as was tested up to November 1958. The fuel is completely replaced with fuel cartridges of the same design. Most of the moderator assemblies were salvaged. However, all moderator assemblies were modified slightly to correct an interference condition. The control rod guide tubes also required partial replacement. Limitations in operating procedure are more explicitly defined. These, and the modifications in design, are described in detail. Further information concerning the probability and seriousness of reactor accidents is also included. (auth)

• Research Organization: General Electric Co. Aircraft Nuclear Propulsion Dept., Cincinnati
• DOE Contract Number: AT(11-1)-171
• NSA Number: NSA-16-006094
• OSTI ID: 4820991
• Report Number(s): APEX-482
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
AIRCRAFT
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
EXCURSIONS
FAILURES
FUEL CANS
FUEL ELEMENTS
HEAT TRANSFER
MATERIALS TESTING
MODERATORS
NEUTRON FLUX
PLANNING
POWER PLANTS
PROPULSION
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RODS
SAFETY
SHUTDOWN
TUBES