QUARTERLY PROGRESS REPORT FOR OCTOBER, NOVEMBER, DECEMBER, 1957

Technical Report · Fri Mar 21 00:00:00 EST 1958

OSTI ID:4301324

Bright, G.O. ed.

Spert 1. Static tests on the B cores werc completed. The control rod worth and temperature coefficient were determined for each of the B cores: the 24 fuel plates/ assembly, 32 assembly core (B-24/32); 18 fuel plates/ assembly, 40 assembly core (B-16/40); and the 12 fuel plates/assembly, 64 assembly core (B-12/ 44). Void coefficient studies were performed on each core, and a slightly positive coefficient was found in the central portion of the B-12/64 core. Flux distributions were measured for each core. The kinetic testing program was initiated and a number of transient experiments were performed, with results yet in the preliminary stage. Data Reduction and Interpretation. Almost all of the usable data from the Spert 1-A core tests have bcen reduced. A cross-index is being set up to facilitate finding desired test data. Reactivity calculations on boiling step-transients continues. Theoretical. Reactor statics calculations on the Spert 1-B core are in progress. These include effects on reactivity of temperature, voids, and excess fuel for each of three fuel assembly types. Calculations were made of the critical mass of a B-type core with D/sub 2/ moderator and reflector, such as might be used in Spert II. Instrumentation. The instrumentation section has completed modification, maintenance, testing, and calibration of basic transient instrumentation for the ''B'' core experiments. A semi-automatic system for calibration of thermocouple channels has resulted in decreased calibration and data reduction time. Now techiques for attaching thermocouples to fuel plates are under test in ''B'' core transient experiments. The area monitoring system was modified for better operation in high humidity conditions. Special projects and investigations include construction and use of a frequency modulated current source, construction of special purpose wide-band a- c amplifiers, construction of a gamma chamber for use in radiation sensitivity tests, and installation of convenience outlets at the reactor pit area which are controlled at the console. Engineering. A review of the system operation indicates that the cold trap for recovery of D/sub 2/ vapor is adequate. A piping modification which will allow use of the small heat exchanger for light water cooling is contemplated. Corrosion studies on aluminum have resulted in the selection of 6061 aluminum for the core structure. Tests on the Spert lfl control rods indicate that redesign of the upper end box section will be necessary because of the large pressure drop across it. Means for reducing flux peaking at the junction of the fuel and poison sections are under investigation. Calculations of the after-shutdown activity indicate that normal shutdown operation can be performed. Studies are in progress on tbe beat transfer characteristics of the reactor and the use of soluble poison for reactor control. (For preceding period see IDO-16416.) (D.E.B.)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-12-015840
• OSTI ID: 4301324
• Report Number(s): IDO-16437
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-58
• Country of Publication: United States
• Language: English

Related Subjects

PHYSICS
ALUMINUM
AMPLIFIERS
ATMOSPHERE
BOILING
BURNOUT
CIRCUITS
CONFIGURATION
CONTROL
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
CORROSION
CRITICALITY
CURRENTS
DISTRIBUTION
EQUATIONS
FUEL ELEMENTS
GAMMA DETECTION
GAMMA RADIATION
HEAT EXCHANGERS
HEAT TRANSFER
HEATING
HEAVY WATER
HEAVY WATER MODERATOR
HUMIDITY
INSTRUMENTS
MAINTENANCE
MASS
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
MODERATORS
MONITORING
NEUTRON FLUX
NUMERICALS
OPERATION
PLANNING
PLATES
POISONING
PRESSURE
RADIATION PROTECTION
RADIOACTIVITY
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTORS
REFLECTORS
RODS
SERVOMECHANISMS
SHUT