States

THERMAL EXPANSION OF URANIUM DIOXIDE. Final Report (open access)

THERMAL EXPANSION OF URANIUM DIOXIDE. Final Report

The thermal expansions of commercial uranium dioxide specimens were measured up to the melting point. The linear expansion of dense, normal grain size UO/sub 2/ follows closely the equationi L = L/sub 0/(1 + 6.0 x 10/sup -6/t + 2.0 x 10/sup -9/t/sup 1.7 x 10/sup -12/t/sup 3/). An anomalous expansion was noted in the temperature range 1000 to 1500 deg C. Above 2500 deg C the rapid vaporization and crystal growth of UO/sub 2/ necessitate the application of heating techniques which provide rapid heating and quenching in order to obtain reliable data. The use of solar and arcmelting furnaces for this type of measurement is described. (auth)
Date: April 15, 1959
Creator: Halden, F.A.; Wohlers, H.C. & Reinhart, R.H.
Object Type: Report
System: The UNT Digital Library
Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958 (open access)

Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958

The ambient temperature of the Columbia River is of interest to the Aquatic Biology Operation since it provides a basis for controlling the temperatures in various experimental tanks which contain Columbia River organisms and since it provides some indication of whether conditions are favorable for the valuable species of fish living in the river. Since the start-up of the plant, temperatures of the river water have been taken in the several water treatment plants.
Date: April 15, 1959
Creator: Foster, R. F.
Object Type: Report
System: The UNT Digital Library
FEASIBILITY OF PARTIAL CHEMICAL CONTROL FOR THE SM-2. SM-2 (FORMERLY APPR- 1B) DESIGN PROGRAM, TASK 12-CHEMICAL CONTROL (open access)

FEASIBILITY OF PARTIAL CHEMICAL CONTROL FOR THE SM-2. SM-2 (FORMERLY APPR- 1B) DESIGN PROGRAM, TASK 12-CHEMICAL CONTROL

Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution and reducing the number of control rods by supplementing the burnable poison with chemical control was also demonstrated. A preliminary design of an injection and removal system was prepared for the SM-2. (auth)
Date: May 15, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories Operation monthly activities report, April 1959 (open access)

Hanford Laboratories Operation monthly activities report, April 1959

This is the monthly report for the Hanford Laboratories Operation, April, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities. Biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation programming, radiation protection, and laboratory auxiliaries operation are discussed.
Date: May 15, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
COATING OF GRAPHITE WITH SILICON CARBIDE BY REACTION WITH VAPOR OF CONTROLLED SILICON ACTIVITY (open access)

COATING OF GRAPHITE WITH SILICON CARBIDE BY REACTION WITH VAPOR OF CONTROLLED SILICON ACTIVITY

In the reaction of silicon halides with graphite to form silicon carbide, thermodynamic conditions were determined for the formation of SiC, free of elemental silicon. The use of these conditions was designed to limit the rate of coating formation by the rate of diffusion of carbon through the coating, and render the operation independent of the vapor-flow factors which normally limit the uniformity of vapor-deposited coatings. Although a wide range of pressure- temperaturecomposition conditions was explored, it was not possible to duplicate the success previously obtained in applying the method to NbC, TaC, TiC, and ZrC coatings. Fundamental differences in the characteristics of the carbides which may account for the difference in behavior are the lack of a range of homogeneity in beta SiC crystal structure, and the fact that SiC undergoes a modification from the cubic beta to a hexagonal form at l900 to 2000 deg C.There remains the prospect of forming a uniform SiC ''sponge'' by the present process which can be subsequently impregnated with metallic silicon to form an oxidation-resistant cpating. (auth) l6200 Preliminary results were obtained on the value that commercially pure Pu (95% Pu/sub 235/ and 5% Pu/subp 240/) has when used as nuclear fuel. …
Date: June 15, 1959
Creator: Blocher, J.M. Jr.; Leiter, D.P. Jr. & Jones, R.P.
Object Type: Report
System: The UNT Digital Library
Containment Properties of DCX (open access)

Containment Properties of DCX

The ''absolute'' containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confine;, ment in space and momentum are plotted for 300-kev deuterons. (auth)
Date: June 15, 1959
Creator: Fowler, T K & Rankin, M
Object Type: Report
System: The UNT Digital Library
Containment Properties of DCX (open access)

Containment Properties of DCX

The "absolute" containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confinement in space and momentum are plotted for 300 Kev deuterons.
Date: June 15, 1959
Creator: Fowler, T. K. & Rankin, M.
Object Type: Report
System: The UNT Digital Library
Division of Reactor Development Programs Monthly Report- May 19599 (open access)

Division of Reactor Development Programs Monthly Report- May 19599

Plutonium Fuels Development Basic studies. Experiments to determine the effect of plutonium dioxide additions on the sinterability of UO2 have continued. PuO2 has been added to ball milled PWR grade UO2 as a physical mixture, and in the form of the mixed crystal oxide.
Date: June 15, 1959
Creator: Lewis, M.
Object Type: Report
System: The UNT Digital Library
Gamma energy analysis of the RMA Line and Recuplex (open access)

Gamma energy analysis of the RMA Line and Recuplex

Knowledge has developed steadily over the past 18 months toward defining the characteristics of the gamma and neutron radiation associated with plutonium and its compounds. Laboratory measurement have been made on plutonium samples taken from the RMA Line, film badge studies have been made in plutonium processing areas, and calculations have been made predicting dose rates and shielding requirements at higher plutonium exposure levels. As these studies continue, and more precise data is accumulated, it will be possible to (1) more accurately evaluate the radiation received by operating personnel, and (2) more accurately (and economically) specify shielding for facilities designed for processing high exposure plutonium. This report gives the results of a gamma energy analysis of the RMA Line and Recuplex obtained with a laboratory model gamma spectrometer. Measurements have been made in the 234-5 Building which have defined the general gamma energy spectrum emitted by the plutonium processing hoods on the RMA Line and in Recuplex. The data obtained from this study has helped resolve the discrepancy between laboratory data and film badge data, and has provided additional information to help in prediction of the gamma radiation levels to be expected from plutonium irradiated to 2000 MWD/T (NPR) and …
Date: June 15, 1959
Creator: Brown, C. L.
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories Operation Monthly Activities Report: May 1959 (open access)

Hanford Laboratories Operation Monthly Activities Report: May 1959

This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.
Date: June 15, 1959
Creator: Hanford Laboratories
Object Type: Report
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Letter Report No. 7 Covering Period April 1 to May 31, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Letter Report No. 7 Covering Period April 1 to May 31, 1959

Progress is reported on the development of a cyclone which will remove particles larger than 8 microns. A method is proposed for a more efficient separation of particles by increasing the number of size separation filters in the sampling train. Preliminary tests with submicron polystyrene particles are being conducted. Numerous methods have been tried for counting the particles in a water droplet of the polystyrene aerosol. The criteria for a satisfactory method of counting particles are discussed. A proposed method to accomplish this is to use carbon-14 labeled polystyrene hydrosols. (For preceding period see ARF-3127-6.) (B.O.G.)
Date: June 15, 1959
Creator: Stockham, J. D. & Rosinski, J.
Object Type: Report
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959

Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."
Date: June 15, 1959
Creator: Stockham, John D. & Rosinski, John
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-642 (open access)

Texas Attorney General Opinion: WW-642

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Article 7047a-19 as amended, Admission Tax liability where admission of patron is by sales slip of required amount.
Date: June 15, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-643 (open access)

Texas Attorney General Opinion: WW-643

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Is it incumbent upon the tax assessor of the Skidmore-Tynan Rural High School District No. 36 to prepare the tax rolls and receipts for taxes collected by the Bee County Tax Collector in behalf of such school district, or is the Bee County Tax Collector required to prepare such tax rolls and receipts.
Date: June 15, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-644 (open access)

Texas Attorney General Opinion: WW-644

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Under the Meat Inspection Law, Article 4476-3 Vernon's Civil Statutes, and the General Appropriation Act, may the Department of Health grant compensatory time to inspection employees?
Date: June 15, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-645 (open access)

Texas Attorney General Opinion: WW-645

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: In the event an insurance carrier makes a payment to the Second Injury Fund, as provided by Sec. 12c-2(a), Art. 8306, Vernon's Civil Statutes, and a "person entitled to compensation" later proves a valid survivor of the deceased employee, can a refund of the payment to the Second Injury Fund be voluntarily made to the insurance carrier by the Industrial Accident Board.
Date: June 15, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-646 (open access)

Texas Attorney General Opinion: WW-646

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Questions relating to Engineering Fee for Design of Filter Systems for Swimming Pools in three State Parks for the State Parks Board.
Date: June 15, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Thermal Diffusion Development Design of Experiments (open access)

Thermal Diffusion Development Design of Experiments

The Facilities Engineering Operation of the Chemical Processing Department prepared a process study scope design of a large thermal diffusion plant for xenon isotope separation. This scoping was done perforce on the basis of calculations made from exclusively theoretical considerations because actual design data are not available. The designers are of the opinion, however, that, such a basis is not adequate to justify the construction of the plant and have, therefore, requested that an appropriate supporting research and development program be carried out. This report presents an experimental plan for obtaining the data required. Anticipated results from the proposed experiments as outlined below, are expected to be useful for determining the correlation of thermal diffusion column theory with practice for this particular system of xenon isotopes. An interpretation of the data will permit the determination of the sensitivity of the column parameters to the change in operational and design variables over which the designer and operator have control. Basic observations made on the behavior of xenon may, in addition, be of general scientific and technological interest. Included in the report are estimates of the kind and quantity of data to be obtained, the analytical services required, and the total analytical …
Date: June 15, 1959
Creator: Brandt, H. L.
Object Type: Report
System: The UNT Digital Library
Thermal Diffusion Development Design of Main Equipment (open access)

Thermal Diffusion Development Design of Main Equipment

This paper presents a scope design of two coaxial type thermal diffusion columns. These experimental columns are proposed to meet the requirements of the research and development program given in Part 2 of this report series. They would rearrange the isotopes of xenon from the Case II product of the Purex Gas Separations Facility to yield a product with a composite neutron absorption cross section of less than one barn. The theoretical basis for the design is given in Part 1. The auxiliary equipment necessary for the operation and control of the columns is described in Part 4. Major components of the columns and their functions are described in this part, The proposals for the materials of construction and the heating systems are not conclusive. Several possibilities for these requirements, however, are included. The design of two experimental thermal diffusion columns is given to meet the needs of a proposed research and development program for rearranging the isotopes of xenon. The proposed columns are six meters in length and have a maximum diameter of about five inches. They could be built at Hanford for an estimated cost of $10,000.
Date: June 15, 1959
Creator: Brandt, H. L.
Object Type: Report
System: The UNT Digital Library
Thermal diffusion development design parameter calculations for a pilot thermal diffusion apparatus. Part 1 (open access)

Thermal diffusion development design parameter calculations for a pilot thermal diffusion apparatus. Part 1

Atomic Energy Commission has expressed interest in obtaining xenon with a composite neutron absorption cross section of less than one barn. This material may be obtainable from the off-gas of the Purex dissolver. A proposed gas purification facility would process the Purex off-gas through two distillation steps for isolation of a ``rough`` cut of xenon isotopes containing principally Xe{sup 131}, Xe{sup 132}, Xe{sup 134}, Xe{sup 136}, and a small quantity of krypton. This material would become the feed stream for a thermal diffusion plant for xenon isotope separation. Thermal diffusion has been shown to be the most economical way to concentrate the two heavier xenon isotopes of low cross section and to reject the krypton along with lighter xenon isotopes of high cross section. The objective of the work herein reported was to provide the basis for (l) a scope design of pilot thermal diffusion equipment and (2) design of experiments to be made with this equipment. In the absence of experimental data, the pilot design was developed from theoretical considerations of the parameters considered important in thermal diffusion column operations. It was assumed that the pilot unit would have to provide information on the correlation of theory with practice …
Date: June 15, 1959
Creator: Brandt, H. L.
Object Type: Report
System: The UNT Digital Library
The control of beryllium hazards (open access)

The control of beryllium hazards

From abstract: "The toxicological properties of beryllium and compounds of beryllium are briefly reviewed, together with the historical development of the recommendations for maximum permissible beryllium air concentrations. The application of the enclosure technique presently in use at this laboratory for the control of beryllium hazards is described... Monitoring procedures used to evaluate the performance of enclosures are discussed."
Date: July 15, 1959
Creator: Lindeken, Carl L. & Meadors, Orville L.
Object Type: Report
System: The UNT Digital Library
THE CONTROL OF BERYLLIUM HAZARDS (open access)

THE CONTROL OF BERYLLIUM HAZARDS

The toxicological properties of beryllium and compounds of beryllium are briefly reviewed, together with the historical developmert of the recommendations for maximum permissible beryllium air concentrations. The application of the enclosure technique for the control of beryllium hazards is described. Emphasis is placed on the design objectives of partial and total enclosures and the related function of auxiliary components. Monitoring procedures used to evaluate the performance of enclosures are discussed. (auth)
Date: July 15, 1959
Creator: Lindeken, C. L. & Meadors, O. L.
Object Type: Report
System: The UNT Digital Library
Determination of Oxygen in Oxide Films by Neutron Activation Analysis (open access)

Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities masked F18 in the aluminum. It is concluded that a 1 A (0.01 μgm/cm^2) oxide film thickness may be measured by a neutron irradiation at a flux of 10^14 n/cm^2/sec but chemical separation of induced radioactivity from the bulk metal is essential.
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Object Type: Report
System: The UNT Digital Library
Determination of Oxygen in Oxide Films by Neutron Activation Analysis (open access)

Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Preliminary experiments were conducted to evaluate the use of the nuclear reactions Li/sup 6/ (n, alpha )H/sup 3/ and O/sup 16/(H/sup 3/,n) F/sup 18/ to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10/sup 11/ n/cm/sup 2//sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F/sup 18/ of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities masked F/sup 18/ in the aluminum. It is concluded that a 1 A (0.01 mu gm/cm/sup 2/) oxide film thickness may be measured by a neutron irradiation at a flux of 10/sup 14/ n/cm/sup 2//sec but chemical separation of induced radioactivity from the bulk metal is essential. (auth)
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Object Type: Report
System: The UNT Digital Library