Chemical Processing Department Monthly Report: November 1960 (open access)

Chemical Processing Department Monthly Report: November 1960

This report, from the Chemical Processing Department at HAPO for November 1960, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: December 21, 1960
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
System: The UNT Digital Library
Temperature Distribution, Moderator and Reflector Reactor Core (open access)

Temperature Distribution, Moderator and Reflector Reactor Core

Studies were made to determine revised moderator coolant flow requirements in the EGCR core for the latest design. The temperature distribution in the graphite columns was also determined. The total moderator coolant flow was calculated to be 24,024 lb/hr and 31,020 lb/hr for full power and maximum anticipated power, respectively. It was concluded that the maximum moderator temperature (1220 deg F average over the cross section), at full power operation, occurs near the peak heat flux at a location 6.25 to 7.25 ft from the bottom of the active core. The temperature in most of the graphite columns varies from 555 to 1150 deg F over the lower half of the column and 1150 to 990 deg F over the top half of the column. The maximum surface temperature is less than 1110 deg F. Temperature distributions are shown on graphs. (M.C.G.)
Date: December 21, 1960
Creator: Cheng, F.
System: The UNT Digital Library
In-Pile Corrosion Test Loops for Aqueous Homogeneous Reactor Solutions (open access)

In-Pile Corrosion Test Loops for Aqueous Homogeneous Reactor Solutions

An in-pile corrosion test loop is described which is used to study the effect of reactor radiation on the corrosion of materials of construction and the chemical stability of fuel solutions of interest to the Aqueous Homogeneous Reactor Program at ORNL. Aqueous solutions of uranyl sulfate are circulated in the loop by means of a 5-gpm canned-rotor pump, and the pump loop is designed for operation at temperatures to 300 ts C and pressures to 2000 psia while exposed to reactor radiation in beam-hole facilities of the LITR and ORR. Operation of the first loop in-pile was begun in October 1954, and since that time 17 other in-pile loop experiments were completed. Design criteria of the pump loop and its associated auxiliary equipment and instrumentation are described. In-pile operating procedures, safety features, and operating experience are presented. A cost summary of the design, fabrication, and installation of the loop and experimental facillties is also included. (auth)
Date: December 21, 1960
Creator: Savage, H.C.; Jenks, G.H. & Bohlmann, E.G.
System: The UNT Digital Library