The Abundance of the Principle Crustacea of the Columbia River and the Radioactivity They Contain (open access)

The Abundance of the Principle Crustacea of the Columbia River and the Radioactivity They Contain

The following document describes data collected from a 14-month period of analyzing crustaceans containing radioactivity. Provided is information based on the change of radioactivity through seasonal changes.
Date: June 25, 1953
Creator: Coopey, R. W.
System: The UNT Digital Library
Coating Removal Waste Loss Reduction : Final Report, Production Test 221-B-8 (open access)

Coating Removal Waste Loss Reduction : Final Report, Production Test 221-B-8

The following report covers a test with the objective to demonstrate that the plutonium and uranium losses associated with the aluminum jacket dissolution could be reduced by substituting a water wash for the 5 per cent nitric acid wash following the coating removal and that this change would not adversely effect the product yield of decontamination in subsequent process steps.
Date: June 25, 1951
Creator: Kirkendall, B. E.
System: The UNT Digital Library
A Martensitic Reaction for Uranium (open access)

A Martensitic Reaction for Uranium

Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.
Date: June 25, 1957
Creator: Bement, A. L. & Wallace, W. P.
System: The UNT Digital Library
The Reactivity Value of Highly Burned Plutonium in Thermal Reactors (open access)

The Reactivity Value of Highly Burned Plutonium in Thermal Reactors

It has been suggested by many workers in the power reactor field that a more efficient utilization of natural uranium may be obtained in thermal reactors if the Pu produced in a fuel cycle were used to enrich a subsequent cycle in which the irradiation-depleted-uranium would be reirradiated. The work described here was done for the purpose of evaluating the reactivity value of the Pu enrichment under the assumption that all plutonium produced is, after chemical separation, fabricated into separate fuel elements and not alloyed with recycled uranium. It has been suggested that the reactivity value of the Pu decreases with exposure to such an extent that highly burned plutonium should be discarded. We, therefore, wish to look at two of the variables affecting the limiting exposure: the reactivity value of the fuel as a function of exposure and temperature and the fraction of potential fissions which would be discarded as a function of exposure. Though the residence time of the Pu fuel before reprocessing, refabrication, and recycling depends upon the relative decrease in specific power, decrease in reactivity due to fission product build-up, the lifetime of the fuel elements before failure, and the cost of reprocessing, only the first …
Date: June 25, 1956
Creator: Heineman, R. E. & Lefevre, H. W.
System: The UNT Digital Library
Report of Invention The Preparation of Uranium Dioxide by Fused Salt Electrolysis (open access)

Report of Invention The Preparation of Uranium Dioxide by Fused Salt Electrolysis

This is a report of what may be an invention in the preparation of uranium dioxide of a quality particularly useful for the fabrications of fuel elements for nutronic reactors.
Date: June 25, 1959
Creator: Lyon, W. L.
System: The UNT Digital Library
The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation (open access)

The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation

An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.
Date: June 25, 1953
Creator: Newell, Donald M.
System: The UNT Digital Library
Static Corrosion Tests of Fabrication Material for D-12 Waste Evaporator (open access)

Static Corrosion Tests of Fabrication Material for D-12 Waste Evaporator

Three types of stainless steel (309 SCB, Carpenter 20, 304-L) were exposed to both the liquid and vapor phase of each of three types of solutions. The time of exposure totaled ten days during which the specimens were cleaned and weighed periodically. The three synthetic D-12 waste solutions contained respectively chrome-high chloride, chrome-low chloride and high chloride sans chromium. The solutions were renewed at each weighing.
Date: June 25, 1953
Creator: Barnes, R. G.
System: The UNT Digital Library