Chemical Processing Department Monthly Report: July 1957 Page: 74 of 107
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Research and Engineering 1 HW-5180 2L
PUREX PROCESS TECNOL0GY
Irradiated uranium with exposure rates of 4.2 to 6.5 MJ/T (300 to 633 MWD/T)
and cooling t iIIIls of 101 to 139 days was dissolved and prepared as solvent ex-
traction feed during the month. After a test dissolving of one nine-ton
charge of 92-day "cooled" material, which had been added to a normal dissolver
heel, failed to produce sufficient iodine to detect in samples taken down-
stream of the prototype dual-pass silver reactor, eighteen tons of 72 to 84-day
"cooled" uranium were charged to an empty dissolver. Again samples taken for
radioiodine analyses at the midpoint and downstream samplers of the prototype
reactor were below detectable limits, although more than twice the normal
amount .of uranium has been dissolved without a reactor regeneration. Based
on overall plant iodine emission data during the test, the efficiency of the
prototype dual-pass silver reactor at the present time is greater than 99.99
per cent. A subsequent eight-fold increase in iodine discharge from the stack
was attributed to increased iodine released from the vessel vent system (the
silver reactor is presently out of service) during processing of the short
Typical performance of the solvent extraction cycles during the month is tabu-
Log Decontamination Instantaneous Waste-
Factor, dF Loss, Per Cent
SUranium Plutonium Uranium Plutonium
Precycle 3.4 3.4 (a) 0.33
Partition 1.1 1.7 (a) 0.18(IBU-0.04 )
Final 3.2 3.1 0.004 0.04
Overall T-7 8.2 -- 0.55
(a) No uranium analysis.
The overall decontamination performance of the plant was excellent during the
month in spite of decreased decontamination in the HC and IC Columns due to
temporarily poor interface control. Poor response of the 2A Column interface
probe also continued to be a problem; however, the decontamination and recovery
performance of the column has not been appreciably affected. Reduced pulse
frequency and increased 2AF temperature (400 to 50*C) were used to stabilize
All batches of both plutonium and uranium 1et specifications except the final
batch of plutonium (See Plutonium Concentration); however, the gamma activity
of the uranium product increased to the upper limit just prior to shutdown.
A hot five per cent sodium carbonate flush of the 2D Column failed to reduce
the gamma ratio of the uranium product to normal (0.4 to 0.5) at startup, but
decontamination performce became normal after several days of operation.
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Hanford Atomic Products Operation. Chemical Processing Department. Chemical Processing Department Monthly Report: July 1957, report, August 22, 1957; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1312193/m1/74/: accessed May 21, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.