Accumulation of Radioactivity in Columbia River Fish in the Vicinity of the Hanford Works (open access)

Accumulation of Radioactivity in Columbia River Fish in the Vicinity of the Hanford Works

Abstract: The data obtained from the radioassay of fish collected in vicinity of the Hanford Works between April, 1948 and June, 1950 are presented. Most of the radioactivity in the fish resulted from the concentration of p32 in the scales, bone, and certain visceral organs. The level of activity density in the fish was influenced by size, feeding habits and metabolic rate in addition to the activity density of the water. Changes in operation of nuclear reactors have resulted in progressive increases in activity densities of fish from one year to the next. The levels of radioactivity are not sufficiently high to be hazardous to either the fish or persons eating them.
Date: July 1, 1952
Creator: Olson, P. A., Jr. & Foster, Richard F.
System: The UNT Digital Library
Analytical procedures for the plutonium Metal Fabrication Process (open access)

Analytical procedures for the plutonium Metal Fabrication Process

Report describing the results of the cupferron extraction-copper spark method in determining the impurity elements in plutonium metal. This was required the 234-5 Project analytical program.
Date: July 25, 1952
Creator: Bierlein, T. K.; Kendall, L. F. & Van Tuyl, H. H.
System: The UNT Digital Library
Analytical Procedures for the Plutonium Metal Fabrication Process (open access)

Analytical Procedures for the Plutonium Metal Fabrication Process

Report describing methods of determining trace impurities in plutonium in connection with the Metal Fabrication Process. The methods included are the cupferron extraction-copper spark method and the direct copper spark method.
Date: July 25, 1952
Creator: Bierlein, T. K.; Kendall, L. F. & Van Tuyl, H. H.
System: The UNT Digital Library
Application of Plastic Bags and Sheeting for Operation and Maintenance Across a Contamination Barrier (open access)

Application of Plastic Bags and Sheeting for Operation and Maintenance Across a Contamination Barrier

The following document describes the usage of Vinylite or plastic sheeting for operation and maintenance across a contamination barrier, presenting ecological advantages, photos of special equipment and techniques used during procedure, and the purpose of eliminating open air transfer in contaminated area.
Date: 1952
Creator: Moulthrop, H. A.
System: The UNT Digital Library
Autoclaving of Anodized Slug Jackets (open access)

Autoclaving of Anodized Slug Jackets

The purpose of the test used to make this report was to determine if anodizing could become a part of the canning operation prior to autoclaving, other factors permitting, or if it must follow autoclaving.
Date: September 16, 1952
Creator: Dalrymple, R. S.
System: The UNT Digital Library
Behavior of S.I.R. Fuels Irradiated in Sodium: Final Report, Production Test 105-180-P (Special Request KAPL-79: The "Beta Experiment") (open access)

Behavior of S.I.R. Fuels Irradiated in Sodium: Final Report, Production Test 105-180-P (Special Request KAPL-79: The "Beta Experiment")

Report describing the effects of pile irradiation on fuel materials and coil springs for the Submarine Intermediate Reactor. The investigation was called for by Hanford Irradiation Request No. 79. Results of investigation are detailed in the report.
Date: August 12, 1952
Creator: Lambert, J. B., 1929-
System: The UNT Digital Library
Briquetting of machine plutonium turnings for recycle to the casting operation : final report - production test 235-6 (open access)

Briquetting of machine plutonium turnings for recycle to the casting operation : final report - production test 235-6

Report describing alternative methods for depleting a large turnings inventory in a short period of time.
Date: November 7, 1952
Creator: Chandler, B. A.; Peterson, R. E.; Lefevre, H. W.; Culvahouse, J. W. & Friesen, W. J.
System: The UNT Digital Library
Corrosion of Aluminum in Alum Coagulated Process Water (open access)

Corrosion of Aluminum in Alum Coagulated Process Water

The following report provides the results of an accelerated corrosion test that was performed to compare the effect of two coagulants on the corrosion rates of aluminum slug jacket alloy and 72S. Additionally, some analytical data on the water from the two treatments were obtained and are presented in this report.
Date: January 22, 1952
Creator: Dalrymple, R. S.
System: The UNT Digital Library
Corrosion Test of Type 502 Stainless Steel (open access)

Corrosion Test of Type 502 Stainless Steel

The following report provides complete data and test procedure from hot water corrosion tests of type 502 stainless steel.
Date: August 13, 1952
Creator: Zimmerman, D. L.
System: The UNT Digital Library
Corrosion Tests : SAE 1010 Mild Steel in Synthetic Neutralized Redox Waste Solution (open access)

Corrosion Tests : SAE 1010 Mild Steel in Synthetic Neutralized Redox Waste Solution

From introduction: "This report gives the results of a 1000-hour corrosion test of SAE 1010, low carbon steel, in synthetic Redox waste solutions...The present test was designed to obtain corrosion rates for waste solution temperatures of 180 F, 200 F, and 220 F in solutions neutralized to pH values of 11, 12, and 13.
Date: November 13, 1952
Creator: Endow, Noborn
System: The UNT Digital Library
Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs (open access)

Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs

Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."
Date: September 11, 1952
Creator: Erkman, John O.
System: The UNT Digital Library
A Description of the Acetone-Dye Solution Method of Demarcating a Leak Process Tubing While in the Pile (open access)

A Description of the Acetone-Dye Solution Method of Demarcating a Leak Process Tubing While in the Pile

Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."
Date: July 16, 1952
Creator: DeHollander, W. R.
System: The UNT Digital Library
Design Considerations for a Lattice Test Pile (open access)

Design Considerations for a Lattice Test Pile

From abstract: "The present paper proposes a lattice test pile, (or LTP) as an alternate to the continuing program of building up and tearing down of exponential piles."
Date: July 28, 1952
Creator: Horning, W. A.
System: The UNT Digital Library
Determination of Americium (open access)

Determination of Americium

The following report describes a successful procedure used for the determination of americium in the presence of plutonium. Provided are articles listed that describe the research done in developing the method.
Date: October 15, 1952
Creator: Schmidt, H. R.
System: The UNT Digital Library
The Determination of Americium in Plutonium Product Solutions (open access)

The Determination of Americium in Plutonium Product Solutions

The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.
Date: August 15, 1952
Creator: Chetham-Strode, A., Jr.
System: The UNT Digital Library
The Determination of U²³⁷ and Fission-Product Contamination in Uranium Recovered by the Redox Process (open access)

The Determination of U²³⁷ and Fission-Product Contamination in Uranium Recovered by the Redox Process

Introduction: "When uranium slugs are irradiated in the Hanford piles, one of the many substances formed is U-237. It arises primarily from the reaction: U-238 (n,2n) U-237. This uranium isotope is a beta and gamma emitter with a half-life of 6.7 days. Because it is isotopic with U-238, it accompanies the uranium recovered by the Redox Process, and its concentration is, of course, not diminished by the fission-product decontamination cycles. As a consequence, the maximum total decontamination of irradiated uranium which can be achieved depends upon the quantity of U-237 present in the processed uranium."
Date: October 1, 1952
Creator: Leboeuf, M. B.
System: The UNT Digital Library
Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford (open access)

Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford

Introduction: "During the early planning of the multicurie cells at Hanford it was decided that a slave type manipulator would be necessary to perform the experiments for which the cells were being designed. The design required steel roofs for installation through a port hole in the face. Technical Services Equipment Development began developing the proposed manipulator in January 1951 by making a study of those existing at that tune. None met the requirements which had been established; therefore, the design of a special manipulator was started immediately."
Date: October 31, 1952
Creator: Field, Richard E. & Gifford, John F.
System: The UNT Digital Library
Diffusion Length Measures in the DR and H Piles (open access)

Diffusion Length Measures in the DR and H Piles

The following report investigates tests on diffusion length and contamination performed on graphite laid up in 105-DR and 105-H piles.
Date: August 1952
Creator: Montgomery, E. B.
System: The UNT Digital Library
Elimination of the Cold Outgassing for the Casting Operation : Final Report-Production Test 235-1 (open access)

Elimination of the Cold Outgassing for the Casting Operation : Final Report-Production Test 235-1

Objective: "Production Test 235-1 and an amendment, were written to outline the procedures for reducing the outgassing time and evaluating the effects of these reductions."
Date: January 25, 1952
Creator: Carlson, R. A.
System: The UNT Digital Library
Examination of Discharged Process Tubes (open access)

Examination of Discharged Process Tubes

Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."
Date: July 21, 1952
Creator: Dalrymple, R. S.
System: The UNT Digital Library
The formation of chemical film deposits on aluminum surfaces (open access)

The formation of chemical film deposits on aluminum surfaces

From abstract: "The purpose of this investigation was to establish basic rates of formation of chemical films deposited on aluminum surfaces from water flowing over such surfaces. It was desired to obtain specific information, within certain ranges, as to the influence of temperature, water velocity, and type of aluminum on the rate of film formation."
Date: February 1952
Creator: Andrews, R. V.
System: The UNT Digital Library
Graphite surface studies (open access)

Graphite surface studies

This report discusses the the surface characteristics of virgin and irradiated artificial graphites and the changes which occur upon irradiation.
Date: October 10, 1952
Creator: Spalaris, C. N.
System: The UNT Digital Library
Guide to Application of the X-ray Photometer in Chemical Analysis (open access)

Guide to Application of the X-ray Photometer in Chemical Analysis

From summary: "The relative absorptions of X-rays by various substances are listed as a guide to the application of the X-ray photometric method in chemical analysis and to the estimation of interference by extraneous substances."
Date: June 20, 1952
Creator: Lambert, Maurice C.
System: The UNT Digital Library
Heavy Aggregate Investigation (open access)

Heavy Aggregate Investigation

This report follows a manuscript report made in January 11, 1952, and provides results of a survey that gives corrections as well as suggestions for new and local sources of aggregate material in comparison to the original report. These reports were made in response to a heavy desire of improvement in reactor design and shielding.
Date: December 19, 1952
Creator: Brown, R. E.
System: The UNT Digital Library