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Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions

Description: Introduction: "Room temperature and elevated temperature, static immersion and vapor suspicion, corrosion tests were conducted with Duriron, Hastelloy C, and tantalum in hydriotic acid and 234-5 project process supernatant solution (synthetic environments. The data relevant to these tests are contained herein."
Date: February 25, 1949
Creator: Work, J. B. & Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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Corrosion of Austenitic Stainless Steels in MJ-4 Raw Streams

Description: Introduction: "A laboratory investigation of the relative corrosion resistance of several austenitic stainless steels to the RAW stream of the Tributyl Phosphate Waste Metal Recovery Process was made during the first quarter of 1950. The results of this investigation are reported herein; all original data are recorded in laboratory notebook HW-3282-T."
Date: April 25, 1950
Creator: Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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Analytical procedures for the plutonium Metal Fabrication Process

Description: 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.
Partner: UNT Libraries Government Documents Department
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Analytical Procedures for the Plutonium Metal Fabrication Process

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Factors Affecting the Concentration of TBP Plant Wastes

Description: Introduction: "The problem of determining the properties and necessary controls on the TBP Plant waste disposal to eliminate transport line plugging and to permit higher concentration prior to return of this to the tank farms was studied. A report of preliminary findings was made to L. W. Finsh on January 31, 1953. This report compiles information in the aforementioned report and findings since its issuance. Previous studies related to this problem are summarized in the U. R. Technical Manual, … more
Date: March 25, 1953
Creator: Shepard, D. F.
Partner: UNT Libraries Government Documents Department
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Preparation and Properties of RAF Solutions : Low Acid TBP Flowsheets HW Number 4 and HW Number 5

Description: This report follows work with the purposes of determining the minimum amount of nitric acid required to dissolve slurries of stored metal waste, determining the stability of such metastable solutions as a function of their chemical compositions - primarily acidity - versus time and temperature, and to define a feed suitable for a low-acid TBP process flowsheet, and to indicate the range of variations in composition which can be tolerated for plant operation.
Date: July 25, 1950
Creator: Maness, R. F. & Harmon, M. K.
Partner: UNT Libraries Government Documents Department
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Coating Removal Waste Loss Reduction : Final Report, Production Test 221-B-8

Description: 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.
Partner: UNT Libraries Government Documents Department
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Oxygen Removal with Hydrazine- Interim Report

Description: During normal operation the NPR will function as a closed system and the coolant will be maintained at a high degree of purity. Periodically, however, the system will have to be opened for fuel element discharge and/or decontamination. During these periods the reactor will be operated on single pass cooling. The use of deionized and deoxygenated water as the single pass coolant is not economically feasible due to the large quantities of coolant that will be required. At present it appears that… more
Date: January 25, 1960
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

A Martensitic Reaction for Uranium

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Measurement of the Nuclear Materials Content of Non-Production Fuels

Description: In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date: May 25, 1959
Creator: Schneider, R. A.
Partner: UNT Libraries Government Documents Department
open access

Hastelloy F Dissolver Installation in 321 Building

Description: Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered dur… more
Date: May 25, 1959
Creator: Cooley, C. R.
Partner: UNT Libraries Government Documents Department
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Artificial Cooling of the Columbia River By Dam Regulation Part 1

Description: In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date: May 25, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.

Description: The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected tha… more
Date: February 25, 1959
Creator: Crossman, W.A.
Partner: UNT Libraries Government Documents Department
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Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices

Description: The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solu… more
Date: May 25, 1959
Creator: Nilson, R. & Oakes, T. J.
Partner: UNT Libraries Government Documents Department
open access

Random Loading of E-Metal Dissolver

Description: Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid … more
Date: February 25, 1959
Creator: Ketzlach, M.
Partner: UNT Libraries Government Documents Department
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A Test of the Refraction Seismic Method on the Hanford Project

Description: Information was desired on applicability of seismic methods of geophysical exploration in helping to better define and refine hydrological and geological factors affecting ground disposal of liquid radioactive wastes. To date most of information on the area geology has been obtained from surface mapping and well drilling, although it has long been recognized that geophysical techniques may greatly assist in defining the geology of the region. Although direct measurements are generally preferred… more
Date: September 25, 1959
Creator: Raymond, J. R.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Report on pH Control by Ion Exchange in High pH Systems

Description: The primary purpose of a cleanup system in a recirculating water loop is to maintain the best possible water quality conditions. This is normally accomplished by continuously purifying all or a portion of the coolant. A secondary objective of the cleanup system is to help maintain the system pH at a constant value. A system that will satisfactorily accomplish both of these objectives is at times difficult to obtain. Generally the pH control characteristics are sacrificed in favor of the more im… more
Date: April 25, 1960
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
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