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Production test 234-4, production of plutonium (IV) fluoride by direct hydrofluorination of plutonium (III) oxalate. Final report
A new method for the production of plutonium (IV) fluoride, which is used for the production of metallic plutonium, is described. The method bypasses the oxidation of plutonium(III) oxalate to plutonium(IV) oxide. A production test was executed with favorable yields; the decision to replace the prior method was recommended. This report is from the Hanford Works 234-5 building, March 30, 1951.
Date:
March 30, 1951
Creator:
Quinn, F.J. Jr.
Object Type:
Report
System:
The UNT Digital Library
Correlation of cleanout and estimated product hold-up data - N-1 Nutsches
Data is presented from the separations technology division, May 14, 1951, to compare plutonium recovery from leaches of N-1 to corresponding hold-up data of plutonium.
Date:
May 14, 1951
Creator:
Healy, W.C.
Object Type:
Report
System:
The UNT Digital Library
Analytical results on leachings from Nutsche Filters
This report describes results of an investigation to determine whether plutonium nitrates and lanthanum compounds were being entrained on the filter aid and filter block of the Nutsche Filters in Cell 2 of Bldg. 231. Leach samples were analyzed for La, Pu, phosphate, fluoride, Pu{sup 240}, and Am. From the data the authors concluded that the holdup on the Nutsche Filter is due to insoluble plutonium compounds either filtered from solution, or more likely, formed on the filter. These compounds would have a relatively low solubility in 25% nitric acid and would dissolve slowly, thus permitting a gradual buildup of material on the filter which was not detected until leaching with 60% nitric acid was instituted.
Date:
July 2, 1951
Creator:
Barton, G.B.
Object Type:
Report
System:
The UNT Digital Library
Analysis of supernatants 234-5 Building
The Pu in one batch (160 gms) is precipitated in a purification hood and waste supernatant is then transferred to the storage tank in one of the recovery hoods. Under normal process conditions a small amount of Pu remains in the supernatant. However, it is possible, though extremely unlikely, that the entire 160 grams would be transferred to the waste storage tank. The supernatants are transferred to an evaporator where they are concentrated. This evaporator has dimensions approximately the same as those of the storage tank, however, as concentration proceeds, the remaining solution can pass to a geometry more favorable for a chain reaction. There should be definite assurance before evaporation is begun that the amount of Pu in the evaporator does not exceed 160 grams. It is concluded that there is no objection, from a nuclear safety standpoint, to the discontinuance of analysis of the supernatants.
Date:
August 23, 1951
Creator:
Gast, P.F.
Object Type:
Report
System:
The UNT Digital Library
Constant chemical addition to reduction operation in the 234-5 Building
At the request of the ``S`` Division, a study has been made regarding the feasibility of simplifying operations by standardizing the amounts of chemical additions made at the reduction step as is the current practice in the purification operation. The investigation included a study of the following items, which are discussed under separate headings: (1) variation in feed; (2) maximum variation in booster ratios and per cent excess calcium using the method; and (3) chemicals handling and storage procedures. The process reduces plutonium fluoride to the metal.
Date:
July 29, 1951
Creator:
Quinn, F.J.
Object Type:
Report
System:
The UNT Digital Library
Analyses required for the slag and crucible recovery program
This summary from the analytical research section, May 1, 1951, briefly describes the analytical method to be utilized in the recovery of plutonium from crucibles program.
Date:
May 1, 1951
Creator:
Groot, C. & Hill, O.F.
Object Type:
Report
System:
The UNT Digital Library
Recommendations for the addition of standard quantities of chemicals in certain reduction operations in the 234-5 Building
This report lists recommendations to be adopted in the process for the reduction of plutonium fluorides by calcium metal in order to save time and money in the Plutonium Finishing Plant. These recommendations regard the standardization of procedures for batch operations. Instead of weighing chemicals to be added to each PuF{sub 4} batch, standard quantities of iodine and calcium would be prepared and stored for later use. The reagents would be added to PuF{sub 4} batches in the 410--430 gram range without further weighing.
Date:
September 17, 1951
Creator:
Desposato, F. E.
Object Type:
Report
System:
The UNT Digital Library
List of equipment changes required for the production of various model sizes on the RMA and RMB lines, 234-5 Building
In order to change models on the RM Line, a number of equipment items must be either replaced or modified. Some items may not necessarily require replacement depending upon the severity of the change. The attached list of items will require replacement or modification before production can be shifted from the present model to any of the others previously produced at this plant. The equipment is part of the Remote Mechanical A and B lines of the Plutonium Finishing Plant.
Date:
August 29, 1951
Creator:
Beaulieu, O.F.
Object Type:
Report
System:
The UNT Digital Library
RM line equipment problems associated with a proposed increase in batch size
The effect made on the RM (Remote Mechanical) Line equipment by an increase in the plant batch size from ca. 300 grams to ca. 375 grams has been studied. Using the process as determined by Production Test 234-3, the volumes for a 300 gram batch and a 375 gram batch are as follows, respectively: volume of plutonium peroxide (alcohol washed, filtered)--1,275 cc., 1,593 cc.; volume of plutonium tetrafluoride (as produced)--617.7 cc., 772 cc.; and volume of reduction charge (tamped)--511 cc., 638 cc. The difficulties encountered with 375 gram batches are discussed.
Date:
September 10, 1951
Creator:
Quinn, F. J., Jr.
Object Type:
Report
System:
The UNT Digital Library
Interim report of N-1 tank product recoveries in the 231 Building
This report, from the Hanford Plant, May 11, 1951, describes the filtration of process solution resulting from building 231 activities.
Date:
May 11, 1951
Creator:
Smolen, S. G.
Object Type:
Report
System:
The UNT Digital Library
Addition of standard quantities of chemicals in certain reduction operations in the 234-5 Building
A proposal by ``S`` Division that operations be simplified by adding fixed amounts of calcium and iodine in the reduction step as a time saving device has been investigated. Ten test runs in the 410--430 gram range have been compared with twenty normal runs made in this period. The average yields were 98.27% for the normal method and 98.26% for the test runs. No effect on individual yields by the variance in percent calcium and the iodine ratio was observed. Seventy percent of the runs normally fall into the 410--430 gram range. By controlled compositing of the feed batches, it should be possible to increase the percentage of the PuF{sub 4} runs that fall in this range.
Date:
September 28, 1951
Creator:
Desposato, F.E.
Object Type:
Report
System:
The UNT Digital Library
The relative physiological and toxicological properties of americium and plutonium
The relative physiological and toxicological properties of americium and plutonium have been studied following their intravenous administration to rats. The urinary and fecal excretion of americium was similar to that of plutonium administered as Pu(N0{sub 3}){sub 4}. The deposition of americium the tissues and organs of the rat was also similar to that observed for plutonium. The liver and the skeleton were the major sites of deposition. Zirconium citrate administered 15 minutes after injection of americium increased the urinary excretion of americium and decreased the amount found in the liver and the skeleton at 4 and 16 days. LD{sub 30}{sup 50} studies showed americium was slightly less toxic when given in the acute toxic range than was plutonium. The difference was, however, too slight to be important in establishing a larger tolerance does for americium. Survival studies, hematological observations, bone marrow observations, comparison of tumor incidence and the incidence of skeletal abnormalities indicated that americium and plutonium have essentially the same chronic toxicity when given on an equal {mu}c. basis. These studies support the conclusion that the tolerance values for americium should be essentially the same as those for Plutonium.
Date:
November 15, 1951
Creator:
Carter, R.E.; Busch, E. & Johnson, O.
Object Type:
Report
System:
The UNT Digital Library
Toxicology and radiation hazard of polonium
This report is a bibliography of studies on the toxicology of polonium with focus on issues addressed by the Atomic Energy Commission, but also includes published literature. Some of the citations contain abstracts and the reports are annotated as to contemporary classification status of reports.
Date:
August 13, 1951
Creator:
Sachs, F.L.
Object Type:
Report
System:
The UNT Digital Library
Report for research on substitute materials. Quarterly progress report, April 2, 1951 to July 2, 1951 (Polonium-208)
Mound Laboratory is cooperating on a joint development program directed toward the production of polonium-208 by proton irradiation of bismuth. Because of the greater half life of polonium-208 compared with polonium-210 (2.93 years versus 138.4 days), it would be a desirable substitute for polonium-210, At the present time the Electromagnetic Division of Oak Ridge National Laboratory is operating a cyclotron for the production of polonium-208 on an experimental scale. The targets produced are sent to Mound Laboratory for evaluation of the results which have been obtained, as well as for processing of the targets to obtain experimental amounts of the polonium in a purified form. The California Research Corporation is designing the target to be used in the Mark I linear accelerator located at Livermore, California. The overall responsibility for the Mark I design and operation is being handled by the California Research and Development Corporation. Before it is used for the production of polonium-208, the Mark I will be convert d from a deuteron beam, on which it will first operate, to a proton beam. This report describes progress on separation processes of bismuth and polonium, and diffusion of polonium through aluminium.
Date:
August 6, 1951
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High Pressure Water
This report is the descriptive summary Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High Pressure Water.
Date:
May 1, 1951
Creator:
Jens, W. H. & Lottes, P. A.
Object Type:
Report
System:
The UNT Digital Library