The Determination of Nitrous Oxide with the Infrared Spectrometer (open access)

The Determination of Nitrous Oxide with the Infrared Spectrometer

The following report describes the process of the determination of nitrous oxide with the infrared spectrometer.
Date: January 25, 1950
Creator: Moore, R. H. & Carson, W. N.
System: The UNT Digital Library
A One Year Study of Radioactivity in Columbia River Fish (open access)

A One Year Study of Radioactivity in Columbia River Fish

This report follows studies of the accumulation of beta omitting radioactive elements in Columbia River fish.
Date: October 25, 1948
Creator: Herde, K. E.
System: The UNT Digital Library
Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions (open access)

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

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.
System: The UNT Digital Library
Corrosion of Austenitic Stainless Steels in MJ-4 Raw Streams (open access)

Corrosion of Austenitic Stainless Steels in MJ-4 Raw Streams

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.
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
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
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
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
Factors Affecting the Concentration of TBP Plant Wastes (open access)

Factors Affecting the Concentration of TBP Plant Wastes

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, HW-19140."
Date: March 25, 1953
Creator: Shepard, D. F.
System: The UNT Digital Library
Preparation and Properties of RAF Solutions : Low Acid TBP Flowsheets HW Number 4 and HW Number 5 (open access)

Preparation and Properties of RAF Solutions : Low Acid TBP Flowsheets HW Number 4 and HW Number 5

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.
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
Ultrasonic Testing With Lamb Waves (open access)

Ultrasonic Testing With Lamb Waves

A method is described whereby many types of flaws lying close to the surface of a metal can be ultrasonically detected, regardless of the time duration of the interrogating pulses. Lamb waves are established in the metal between a flaw and the surface by an ultrasonic beam which impinges at the proper angle of incidence. A suitably positioned receiver transducer picks up the waves to reveal the flaw. In this method the usually troublesome surface echo is eliminated from the receiver by an acoustic barrier, making it well suited for routine and automatic testing. Results of applying the technique to several testing problems are discussed.
Date: September 25, 1956
Creator: Worlton, D. C.
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
Neutron Leakage Through Iron (open access)

Neutron Leakage Through Iron

Neutron attenuation in the old pile shields is dependent more and more on the slowing down characteristics of the iron as the hydrogen is baked out of the masonite. For neutrons above 1 or 2 Mev, iron does a good job by inelastic scattering. However, below this energy attenuation can be done only by the gradual moderation by elastic scattering to thermal energies with subsequent capture in the iron. Since iron is heavy and thus a poor moderator, there is a good possibility that many neutrons of intermediate energy will leak out of a burned out shield. Also, iron has a large dip in its cross section at 25 Kev which might allow a large burst of neutrons at this energy to leak out. Measurements using a lucite moderator with gold foil detectors indicate a large leakage of neutrons of intermediate energy, but interpretation of these measurements is difficult. These considerations prompted an attempt to get a rough idea of the energy distribution of the leakage neutrons through pure iron using a simple qualitative theory.
Date: July 25, 1956
Creator: Wood, D. E.
System: The UNT Digital Library
Thermal Expansion of Pile Graphites (open access)

Thermal Expansion of Pile Graphites

Average coefficients of thermal expansion of the temperature range 25 C to approximately 425 C are reported for numerous types of graphite. The dependence of thermal expansion on crystal orientation and crystallite size and the effects of oxidation and cold test hole irradiation are discussed. An empirical relationship between thermal expansion and the initial rate of physical expansion under cold test hole irradiation is formulated.
Date: May 25, 1956
Creator: Riley, W. C. & Woodruff, E. M.
System: The UNT Digital Library
Oxygen Removal with Hydrazine- Interim Report (open access)

Oxygen Removal with Hydrazine- Interim Report

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 filtered water will be used for this purpose. Since filtered water contains substantial amounts of dissolved solids (approximately 100 parts per million), and since it is saturated with air, this type of operation will have to be investigated with regard to corrosion problems. A particularly serious problem will be present after the system has been decontaminated, since the high temperature oxide films will have been removed and the bars metal surfaces will be exposed to the coolant.
Date: January 25, 1960
Creator: Demmitt, Thomas F.
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
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
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
Measurement of the Nuclear Materials Content of Non-Production Fuels (open access)

Measurement of the Nuclear Materials Content of Non-Production Fuels

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.
System: The UNT Digital Library
Hastelloy F Dissolver Installation in 321 Building (open access)

Hastelloy F Dissolver Installation in 321 Building

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 during the fabrication of the vessels.
Date: May 25, 1959
Creator: Cooley, C. R.
System: The UNT Digital Library
Artificial Cooling of the Columbia River By Dam Regulation Part 1 (open access)

Artificial Cooling of the Columbia River By Dam Regulation Part 1

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.
System: The UNT Digital Library
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. (open access)

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.

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 that the reactor operations and radiation monitoring personnel will implement these instructions according to standard operating procedures.
Date: February 25, 1959
Creator: Crossman, W.A.
System: The UNT Digital Library
Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices (open access)

Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices

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 solution of the transport equation such as the P1 and P3 solutions.
Date: May 25, 1959
Creator: Nilson, R. & Oakes, T. J.
System: The UNT Digital Library