REACTOR PROJECTS BRANCH QUARTERLY PROGRESS REPORT FOR JANUARY, FEBRUARY, MARCH, 1958

Technical Report · Wed Sep 10 04:00:00 EDT 1958

OSTI ID:4289706

Bright, G.O. ed.

A number of Spert I transient experiments, both step and ramp, were conducted. During one of the tests a after failure of electrical power to the PRPR primary coolant pumps by the addition of 650 (lb)( sq ft) flywheels to each of the two normally operating pumps. This moment of inertia is based on a 1750 rpm pump please delete the above lines, starting with after failure of ===== portion of a fuel plate was evidently melted, with no adverse effects on the reactor or to personnel. It was determined that the maximum equilibrium power level of the B-12/64 core was 18 Mw, The average void coefficient for the B-12/64 core was measured. Several energy coefficients of the Spert I cores were calculated, using experimental values of void coefficient and temperature coefficient. An investigation of noise observed on thermocouple traces has shown that a mechanicalelectrical transducing mechanism is possible whenever alumel wire is used. Several zero-power reactor transfer functions which were calculated for use in the pile oscillator program are presented. A complete description of the techniques used in calibrating the Spert neutron level detectors in terms of power is presented. The simple Fuch's model for prompt power bursts was extended to include a power law dependence on energy release and a time delay beiween energy release and the appearance of shutdown effects. Comparison with experimental data is presented. The Fuch's model was also extended to the treatment of ramp functions of reactivity addition. The shutdown effects to be expected from fuel plate expansion and direct moderator heating are determined on the basis of experimental values of the void and temperature coefficients. A refinement of the moderator temperature rise calculation was made, Reactivity calculations for possible Spert III cores were made using an IBM- 704. Preliminary shutdown reactivity results are presented, Plans for modification of the Spert I reactor to use APPR fuel assemblies were completed and component construction was initiated. Progress in the construction of the Spert II reactor is detailed, and a description of the reactor internal structure is presented. A summary of the Spert III construction progress, control rod design and test program, and the preparation for some of the engineering tests to be performed on the reactor after acceptance are detailed. (For preceding period see ID0-16437.) (auth)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-13-000441
• OSTI ID: 4289706
• Report Number(s): IDO-16452
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
ALUMEL
ALUMINUM ALLOYS
BURNOUT
COMPUTERS
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
EFFICIENCY
EQUATIONS
EXCURSIONS
EXPANSION
FAILURES
FUEL ELEMENTS
HEAT TRANSFER
HEATING
IBM 704
MANGANESE ALLOYS
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
MELTING
MODERATORS
NEUTRON DETECTION
NEUTRON FLUX
NICKEL ALLOYS
NUMERICALS
PERSONNEL
PLANNING
PLATES
REACTIVITY
REACTOR CORE
REACTOR OSCILLATORS
REACTORS
RECORDING SYSTEMS
RODS
SHUTDOWN
SILICATES
SILICIDES
SM-1
SPERT-1
SPERT-2
SPERT-3
STABILITY
STANDARDS
TEMPERATURE
THERMOCOUPLES
TRANSFER FUNCTIONS
TRANSIENTS
WIRES
ZONES