SPERT PROJECT. Quarterly Technical Report for April, May, June 1959
SPERT I: The characteristics of the boiling process and its relatin to moderator expulsion in Spert I were investigated in a series of capsule type experiments. A fuel-bearing oapsule, instrumented to provide pressure, volume, and temperature data during transient power excursions, was placed in a high flux region of the Spert I P core. Five step-induced transients initiated from boiling indicate that the kinetic behavior of the stainless steel clad P-18/19 core is dependent on initial temperature in a manner similar to that of previously tested aluminum clad spert cores. Reactivity oscillator techniques were used in the P-18/19 core to determine the phase and magnitude of the reactivity-to-power transfer function from 0.01 to 18.4 cps at low power and at temperatures below boiling. Criticality data on relatively simple lattices, both rod-free and containing a single poison rod, were obtained from a series of clean critical experiments performed on a number of light water-moderated and - reflected slab configurations of Spert III fuel elements. Changes in water height during the critical water height experiment were measured to plus or minus 0.0013 inches by means of a simple remoteindicating system designed and built for this purpose. SPERT III: The operational loading was determined to be 44 fuel assemblies and 8 control rods. Experiments revealed that this loading provides about .50 excess at 2500 psi ard 650 deg C and a total rod worth above ambient critical of about .50. Measurements were made of the pressure and temperature coefficients of reactivity and the temperature defect. Apparatus for non-nuclear engineering tests was installed and the tests were initiated to obtain data on core hydraulics, system energy balance, and general plant equipment. A primary coolant sampling station has been added. Experimental apparatus for void experiments was designed and fabrication started. DATA REDUCTION AND INTERPRETATION: A review of previous investigations of boiling and its relation to shutdown effects was made in pursuance of a photographic investigation of shutdown mechanisms. A photographic technique was developed for conducting tests in a fuel-bearing, water-filled test cell in Spert I. A machine program using computed reactivity as input data was used to obtain power solutions tc the kinetics equations. Comparison of the computed and experimental power burst shapes showed the reactivity data and power data to be consistent and in this way has essentially verified the independent program for reactivity calculations. ENGINEERING: Corrosion and galling tendencies were investigated in materials of construction for threaded components used in high temperature demineralized water service. The Spert II primary piping system was completed. Calibrations, check-out, and final tests are in preparation. Work continued on control system wiring, wiring schedules, and schematic drawings. The initial core was accepted. (For preceding period see IDO-16539.) (auth)
- Research Organization:
- Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
- DOE Contract Number:
- AT(10-1)-205
- NSA Number:
- NSA-14-016484
- OSTI ID:
- 4136770
- Report Number(s):
- IDO-16584
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINUM- BOILING- CANNING- CONFIGURATION- CONTROL ELEMENTS- COOLANT LOOPS- CRITICALITY- FREQUENCY- HYDRAULICS- INSTRUMENTS- IRRADIATION- LEVELS- MEASURED VALUES- MOTION- PRESSURE- REACTIVITY- REACTOR CORE- REACTOR OSCILLATORS- REACTORS- SAMPLING- SPERT-1- SPERT-3- STAINLESS STEELS- TEMPERATURE- TRANSFER FUNCTIONS- TRANSIENTS- VOLUME- WATER MODERATOR- - ZONES
BOILING- COMPUTERS- EQUATIONS- EXCURSIONS- PHOTOGRAPHY- PROGRAMMING- - REACTIVITY- SHUTDOWN- VARIATIONS
CIRCUITS- CONTROL SYSTEMS- CORROSION- DIAGRAMS- HIGH TEMPERATURE- PIPES- TESTING- WATER COOLANT