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3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples (open access)

3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples

The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors the radiation data for shielding determination is still frequently inadequate because of wide variations in dose rates resulting from self-absorption. The degree if self-shielding is in turn dependent on nature of the plutonium compound, degree of compactness, weight, and over-all geometrical distribution of the source material. By preparing a variety of plutonium samples representing combinations of these varying factors, actual dose rates and gamma spectra, as obtained from them, can then be extrapolated for application to specific situations.
Date: October 22, 1959
Creator: Moulthrop, H. A.
System: The UNT Digital Library
Composition of Solids from Purex LWW (open access)

Composition of Solids from Purex LWW

The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww that have been studied, and the centrifuged volume of solids has been about four percent in each case.
Date: January 22, 1959
Creator: Van Tuyl, H.H.
System: The UNT Digital Library
Corrosion Data for Type 347 Stainless Steel Pipe Waste Metal Recovery Process (open access)

Corrosion Data for Type 347 Stainless Steel Pipe Waste Metal Recovery Process

Introduction: "A limited test progress for the evaluation of type 347 stainless steel pipe which failed the Huey (?) test has been complicated. The tests reported herein were similar in scope to those reported in document number EW-20765, Corrosion Tests on Stainless Steel Plate, Waste Metal Recovery Process. Material tested was obtained on order number EWC-8553, National Tube Company Heat #3X9741. Lots 9789 and 9790."
Date: May 22, 1951
Creator: Sanborn, Kenneth L.
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
Decontamination of Portable Instruments (open access)

Decontamination of Portable Instruments

The decontamination of portable instruments by the Calibration Unit has presented a problem for some time. Most of the contamination is in the 100 to 500 c/m or 500 to 2000 d/m range. Higher levels of contamination can usually be reduced to these levels, but further cleaning proves quite difficult
Date: May 22, 1953
Creator: Unruh, C. M.
System: The UNT Digital Library
Density and Hydrogen Content of Uranium Oxide Cakes and Slurries (open access)

Density and Hydrogen Content of Uranium Oxide Cakes and Slurries

The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date: March 22, 1960
Creator: Amos, L. C.
System: The UNT Digital Library
Determination of Radiocesium with Chloroplatinic Acid (open access)

Determination of Radiocesium with Chloroplatinic Acid

The following report examines a rapid method used to eliminate the possibility of explosive perchlorate-organic mixtures in a control laboratory in order to determine radiocesium. These methods include the usage of chloroplatinic acid as a precipitate of radocesium.
Date: June 22, 1950
Creator: Erwing, R. E.
System: The UNT Digital Library
Development of a Welding Process for End Closures on NPR and KER Fuel Element (open access)

Development of a Welding Process for End Closures on NPR and KER Fuel Element

With the development of the zircaloy-2 clad uranium fuel element, it was necessary to develop a method of closing the end of the element after the extruded tubes were cut to the desired length. Regardless of the ultimate design of the closure, a satisfactory zircaloy-2 fusion welding technique had to be worked out. The first fully successful welding was performed with electron beam welding in a vacuum chamber. To make satisfactory welds, the electron beam welding involved time and equipment, plus undue maintenance on the equipment.
Date: February 22, 1960
Creator: Corey, T. B.; DeWitt, D. E. & Nelson, I. V.
System: The UNT Digital Library
The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department (open access)

The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department

The major portion of transfers and inventory in the Chemical Processing Department are dependent on volume measurement. Good volume measurements are therefore essential to good SS material control. Considerable attention has been given to the volume problem especially on primary transfer points. Document HW-57888 discusses the biasing effect pf temperature on manometer oil. HW- 57866 given the procedure for vessel calibration. Other undocumented correspondence has discussed recent calibrations and certain aspects of temperature considerations in the volume determinations. However, there is a need to document for future reference the consideration given temperature and provide at the same time information which covers the temperature angle on all volume methods used in the Chemical Processing Department.
Date: May 22, 1959
Creator: Johnson, W. R.
System: The UNT Digital Library
Improved Calibration Facility (open access)

Improved Calibration Facility

Aid in redesign of the calibration facility in order to: 1. Reduce the rate of exposure for calibration personnel below 1 mr/hr; 2. Reduce the rate of exposure outside of the 3745 Building; 3. Reduce the risk of breaking radium sources; 4. Improve the efficiency of calibration procedures by: a. Allowing calibration to be done faster; b. Providing several calibration ranges which can operate simultaneously in the present space allowed; c. Allowing instrument survey work to proceed while calibration work is done. A well-type calibration installation is proposed and a brief description of the required shielding is included.
Date: August 22, 1995
Creator: Roesch, W. C.
System: The UNT Digital Library
In-Line Scintillation Gamma Monitor : Preliminary Specifications (open access)

In-Line Scintillation Gamma Monitor : Preliminary Specifications

From introduction: "The following recommendations represent the best estimate, based on present knowledge, of the requirements for generally applicable or "universal" instrument for the continuous monitoring of radioactive process streams in terms of their gamma activity."
Date: January 22, 1953
Creator: Upson, U. L. & Connally, R. E.
System: The UNT Digital Library
Limitations for Existing Storage Tanks for Radioactive Wastes from Separations Plants (open access)

Limitations for Existing Storage Tanks for Radioactive Wastes from Separations Plants

Continued process improvements in the separation plants provide an incentive for economics in waste storage costs by utilizing existing facilities to their maximum capability consistent with the radiological hazards involved. The major improvements have reduced waste volumes resulting in increased fission product concentration and energy potential. Analyses have been made to determine the effect of this change on the integrity of the existing structures.
Date: October 22, 1959
Creator: Doud, E.
System: The UNT Digital Library
A Microspark Apparatus for the Study of Inclusions in Metals (open access)

A Microspark Apparatus for the Study of Inclusions in Metals

A study of metallurgical problems resulting from variation in grain boundaries, bonding layers, and inclusions in metals and alloys has become increasingly important over the past several years. To keep pace with and aid in these studies, several new techniques have been developed in emission and X-ray spectroscopy. In X-ray, areas as smalls as one square micron can be studied by making them targets for a focused electron beam and observing the X-rays emitted (5,2). Such an instrument would be quite helpful at Hanford, but the high original cost is prohibitive.
Date: July 22, 1959
Creator: Smith, F. M.
System: The UNT Digital Library
Non-destructive Testing Hanford Fuel (open access)

Non-destructive Testing Hanford Fuel

At present, emphasis is being given the application of nondestructive testing to the inspection of nuclear fuel in conjunction with complete product specifications. The objective is to quantitatively specify fuel quality parameters, and to measure the entire fuel production against these specifications nondestructively. Under this concept the acceptability of a given fuel element becomes a well-defined factor readily determined by appropriate nondestructive tests.
Date: June 22, 1960
Creator: Worlton, D.C.
System: The UNT Digital Library
The Oxidation of Plutonium to the Plutonyl State (open access)

The Oxidation of Plutonium to the Plutonyl State

This report follows the study of the oxidation of plutonium III and IV to the plutonyl state.
Date: March 22, 1950
Creator: Miller, H. W. & Brouns, R. J.
System: The UNT Digital Library
Preliminary Report on Existing Active Particle Hazard-200 Areas (open access)

Preliminary Report on Existing Active Particle Hazard-200 Areas

"Recent surveys by the Health Instrument Section have disclosed the presence of many small radioactive spots on ground surfaces in the T and B plant areas. Investigation has shown that representative samples of the spots when mechanically separated invariably end in a single radioactive particle."
Date: October 22, 1947
Creator: Mickelson, M. L.
System: The UNT Digital Library
Preliminary Report on the Ultrasonic Properties of Uranium (open access)

Preliminary Report on the Ultrasonic Properties of Uranium

This report discusses preliminary results acquired from investigations made on the ultrasonic properties of uranium, such as sonic vibrations in the megacycle frequency range.
Date: October 22, 1952
Creator: Worlton, D. C. & Wood, E. C.
System: The UNT Digital Library
The Preparation of Thin Films of Plutonium by Electrodeposition (open access)

The Preparation of Thin Films of Plutonium by Electrodeposition

This report discusses methods for preparing thin films of plutonium on metallic disks, which are used for alpha energy analysis, fission counting, and preparation of geometry standards in ordinary counting. Various methods of preparation were tested and analyzed, but electrodeposition was the most effective method. Deposition was then tested, but the yields were "somewhat erratic".
Date: March 22, 1950
Creator: Miller, H. W. & Brouns, R. J.
System: The UNT Digital Library
Properties of the System: Uranyl Nitrate-Aluminum Nitrate - Nitric Acid (or Sodium Hydroxide) - Sodium Nitrate - Water - Hexone (open access)

Properties of the System: Uranyl Nitrate-Aluminum Nitrate - Nitric Acid (or Sodium Hydroxide) - Sodium Nitrate - Water - Hexone

This report discusses properties of the Redox process. Density, apparent molar volumes and viscosity are all described.
Date: March 22, 1949
Creator: Burger, L. L.; Rehn, I. M.; Schmidt, H. R. & Slansky, C. M.
System: The UNT Digital Library
Protection of Carbon Steel from Atmospheric Corrosion (open access)

Protection of Carbon Steel from Atmospheric Corrosion

The NPR design calls for carbon steel to be the major constituent in the reactor coolant piping system. The piping and its associated fittings will, in all likelihood, be exposed to atmospheric weather conditions during the period of reactor construction. This type of exposure causes rusting. From experience gained during the startup of KER Loop 1 it is expected that there will be initially high NPR coolant activity levels. The high activity during the startup of KER Loop 1 was partially caused by the activation of rust that was eroded from pipe walls. Prevention of rusting on the carbon steel prior to its introduction into the coolant system would reduce the initial activity levels.
Date: October 22, 1959
Creator: Perrigo, Lyle D., Jr. & Moles, R. G.
System: The UNT Digital Library
Pyrophoricity of Uranium in Reactor Environments (open access)

Pyrophoricity of Uranium in Reactor Environments

Report discussing information relative to the pyrophoricity of uranium for the purpose of reactor core fire safety. The report includes physical and chemical properties of uranium.
Date: January 22, 1960
Creator: Zima, G. E.
System: The UNT Digital Library
A Rapid Colorimeric Method for the Determination of Phosphate in Uranium Waste Solutions (open access)

A Rapid Colorimeric Method for the Determination of Phosphate in Uranium Waste Solutions

Report discussing tests of a new colorimetric method. From abstract: "A colorimetric method, which is a modification of the classical phosphomolybdic acid method, has been developed for the determination of phosphate in synthetic uranium waste solutions...The chief advantage of the method, over those presently included in HW Manuals, is the rapidity with which determinations may be carried out."
Date: August 22, 1949
Creator: Sege, C. A. & Ice, C. H.
System: The UNT Digital Library
Soil Column Studies with Radiostrontium I. Effects of Temperature and of Species of Accompanying Ion (open access)

Soil Column Studies with Radiostrontium I. Effects of Temperature and of Species of Accompanying Ion

Soil chemistry studies have been carried on at Hanford for a number of years in support of the disposal of low and intermediate level liquid wastes to the ground. Equilibrium type experiments were carried out to investigate the mechanisms of the reactions of Sr, Cs, and rare earth ions with soils (1, 3, 4, 5). Experiments were also conducted with simulated and actual wastes in soil columns and an empirical method was developed for prediction of radionuclide breakthrough from ground disposal facilities into ground water on the basis of short, laboratory soil columns and equilibrium experiments (6,7). In this method it is assumed that the shape and position of the breakthrough curve is the same under laboratory conditions as in the larger scale field case. It is also assumed that the "column volume" or amount of soil effectively used for fission product sorption is that directly under a disposal facility without considering any spreading of waste solutions. These assumptions are known to be on the conservative side, but the degree of conservativeness is not known.
Date: September 22, 1959
Creator: Nelson, J. L.
System: The UNT Digital Library
Wet Fluoride Studies:  Calcium Plutonium (IV) Fluoride (open access)

Wet Fluoride Studies: Calcium Plutonium (IV) Fluoride

Laboratory studies have shown that the double salt, CaF2-PuF4, can be precipitated by rapid addition of hydro-fluoric acid to solutions containing 25 to 75 g Pu/1, caleium equimolar to plutonium, and 1 to 10 M HNO3. The precipitate, which is subsequently washed with water and dried to 300 degrees C in dehumidified, deoxygenated argon, can be reduced thermally by calcium to give high yields of plutonium metal.
Date: December 22, 1953
Creator: Branin, P. B.
System: The UNT Digital Library