The half life of cesium-137 was determined to be 29.2 plus or minus 0.3 years by an all mass spectrometric method. The abundance of the 662 Kev gamma- ray in the decay scheme was found to be 0.82 plus or minus 0.03 per beta disintegration. In the course of the work, the isotopic distribution of natural barium was determined with improved accuracy to be (72.11 plus or minus 0.06)% 138, (11.18 plus or minus 0.05)% 137, (7.77 plus or minus 0.02)% 136, (6.42 plus or minus 0.03)% 135, (2.33 plus or minus 0.02)% 134, (0.091 plus or minus 0.003)% 132, and (0.098 plus or minus 0.002)% 130. (auth)
Date: June 1, 1962
Creator: Rider, B.F.; Peterson, J.P. Jr. & Ruiz, C.P.
A review is preserted of milking systems for separating a desired radioisotope from its parent and other contaminants. Milking systems are considered for the separation of the following radioisotopes: Zr/sup 95/ from Nb/ sup 95/, I/sup 132/ from Te/sup 132/, La/sup 140/, from Ba/sup 140/ Ba/sup 137/ from Cs/sup 137/ Y/sup 90 / from Sr/sup 90/ Tc/sup 99m/ from Mo/sup 99/, Ga/sup 68/, from Ge/sup 68/, Al/sup 28/ from Mg/sup 28/, etc. (D.L.C.)
Date: January 1, 1962
Creator: Greene, M.W.; Doering, R.F. & Hillman, M.
Three groups of 12 mice each were maintained at environmental temperatures of 34, 22, and 5 deg C for a period of about 7 weeks after an intraperitoneal injection of Cs/sup 137/. Periodic assay of the activity in the whole body and excreta showed that as environmental temperature decreases the excretion of Cs/sup 137/ increases, probably as a result of the increased metabolic rates associated with low temperatures. (auth)
Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 times the flow sheet rate did not inhibit the oxidation of the uranium at this temperature. Batchwise mixing in air of dissolver product solution with complexer solution oxidized the uranium within two minutes at 23 deg C or higher. Further studies of continuous zirconium dissolution indicated that precipitation of uranium at the acid inlet can be a problem, probably because of local concentration gradients of free HF, which result in conditions of low uranium solubility. Control of dissolver acid composition by electrical conductance measurement appeared possible due to the linear relationship of conductance with acid concentration. Aluminum alloy dissolution rates in nitric acid were found to vary significantly, depending on the type and amount of alloying agent. Silicon, nickel, and copper in the alloy significantly decreased the dissolution rate. Batch dissolution times for standard test coupons ranged from 14 minutes for a high purity aluminum to 1400 minutes for an alloy containing 2.9 percent silicon. In the electrolytic dissolution of Nichrome in a bench-scale basket dissolver, the substitution of titanium for niobium as the anode basket material significantly reduced the contact resistance. Current interruption due to contact failure was essentially eliminated, and contact resistance on the titanium was sufficiently low that increasing solution resistance due to acid depletion became a major contributor to current decline as dissolution progressed. The indirect solution-contact electrolytic dissolution principle was further studied, producing data on electrode ...
Cs-137 has been chosen as a possible index of the plutonium and uranium in coating waste. This index is a stable ratio as long as the plutonium formation rate (Pu/MD) is stable. Calculations are presented for Purex and Redox. It is recommended that the Cs-137 index method be used for determining nuclear materials content in coating waste at both Purex and Redox; this will result in higher but more accurate statements of Pu, U losses in coating waste.
This document contains the results of weekly sampling of various isotope concentrations from effluent water at the 100 area at Hanford from July 1962 to February 1965. Compiled data in microcuries/milliliter are given. Each sampling records the concentrations of iodine-131, phosphorus-32, zinc-65, scandium-46, chromium-51, and cobalt-60. Records prior to October 8, 1962 also contain information on strontium-90, cesium-137, zirconium-95, ruthenium-103, ruthenium-106, and strontium-89. These last records are all from F reactor samples.
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