PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR APRIL 1, 1959- JUNE 30, 1959
Annealing, corrosion, and irradiation testing of aluminum base double alloy fuel elements were conducted. Interdiffusion anneals at 500 deg F for periods up to 83 days were accomplished. Heat transfer and fluid flow studies of the heat transfer loop, boiler fuel elements, and the water moderator in the superheater region are discussed. Progress on fuel element fabrication is reported. Welding tests were conducted on the reactor vessel shell and the final design is presented. Progress on the fabrication, installation, and testing of recirculation pumps, steam separators, control rods, guide tubes, and control rod drives is reported. An analysis of control rod worths, core burn-up, boiling effects in superheater, and shielding of fuel handling building is given. A description of the reactor burn-up and decay code (BAD), which has been programmed for the IBM-704, is given. The filter test loop and the radioactive gas decontamination system are described. Instrumentation and control features of the plant are discussed. A plant safety analysis is given. (For preceding period see ACNP-5909.) (C.J.G.)
- Research Organization:
- Allis-Chalmers Mfg. Co. Atomic energy Div., Milwaukee
- NSA Number:
- NSA-14-011286
- OSTI ID:
- 4151786
- Report Number(s):
- ACNP-5915
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BOILING-- FLUID FLOW-- FUEL ELEMENTS-- HEAT TRANSFER-- PATHFINDER-- POWER PLANTS-- SUPERHEATING-- WATER MODERATOR
BURNUP-- COMPUTERS-- CONTROL ELEMENTS-- PATHFINDER-- POWER PLANTS-- PROGRAMMING-- REACTIVITY-- REMOTE HANDLING-- SHIELDING-- SUPERHEATING
CONTROL ELEMENTS-- FABRICATION-- MECHANICS-- PATHFINDER-- POWER PLANTS-- PRESSURE VESSELS-- PUMPS-- STEAM-- TESTING-- TUBES-- WELDING
CONTROL SYSTEMS-- DECONTAMINATION-- FILTERS-- GASES-- INSTRUMENTS-- PATHFINDER-- POWER PLANTS-- REACTOR SAFETY
REACTOR TECHNOLOGY