Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor (open access)

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
System: The UNT Digital Library
Stability of Florothene Under Exposure to Gamma Radiation (open access)

Stability of Florothene Under Exposure to Gamma Radiation

The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date: July 6, 1956
Creator: Adler, K. L.
System: The UNT Digital Library
A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media (open access)

A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media

Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.
Date: August 10, 1953
Creator: Adley, F. E.; Scott, R. H. & Gill, W. E.
System: The UNT Digital Library
Chemical Research Section Progress Report for January 1950 (open access)

Chemical Research Section Progress Report for January 1950

The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
System: The UNT Digital Library
Program Study Report Plutonium Fuel Cycle (open access)

Program Study Report Plutonium Fuel Cycle

From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
System: The UNT Digital Library
Polarographic Analysis of UNH in the IAW Stream (open access)

Polarographic Analysis of UNH in the IAW Stream

The following report describes two rapid, micro methods for the determination of UNH in Redox waste samples that had been developed fir the concentration range 0.2 to 100 g/l.
Date: January 17, 1949
Creator: Alkire, G. J. & Carson, W. N.
System: The UNT Digital Library
Polarographic Determination of Hexone (open access)

Polarographic Determination of Hexone

The following report describes polarographic methods that determine saturated aliphatic carbonyl compounds.
Date: November 10, 1949
Creator: Alkire, George J.
System: The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies (open access)

Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
System: The UNT Digital Library
A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination (open access)

A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination

Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Paper Research Institute of Canada (2) and is designated by them as the Atomized Suspension Technique.
Date: April 28, 1960
Creator: Allemann, Rudolph Theodore
System: The UNT Digital Library
Apparent viscosity of simulated underground metal waste slurries (open access)

Apparent viscosity of simulated underground metal waste slurries

From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."
Date: June 20, 1950
Creator: Allen, A. W.
System: The UNT Digital Library
Clarification of Redox Dissolver Solution by Centrifugation with Scavenger (open access)

Clarification of Redox Dissolver Solution by Centrifugation with Scavenger

From statement of objectives: The purposes of the work described in this report are to provide data useful for designing and operating the dissolver solution clarification equipment to be installed in the Redox production plant.
Date: June 6, 1950
Creator: Allen, A. W.
System: The UNT Digital Library
Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet (open access)

Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet

Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.
Date: August 15, 1950
Creator: Allen, A. W. & Harmon, M. K.
System: The UNT Digital Library
Completion Report An Automatic Fuel Element Stamping Machine (open access)

Completion Report An Automatic Fuel Element Stamping Machine

This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
System: The UNT Digital Library
Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients (open access)

Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stability but also determine many operational characteristics.
Date: December 23, 1959
Creator: Allen, C. W.
System: The UNT Digital Library
Some Comments on the Selection of Operating Temperatures for DPR (open access)

Some Comments on the Selection of Operating Temperatures for DPR

The results of this investigation indicate that maximum electric power generation can be obtained by selecting the turbine steam temperature within a range of plus/minus 30 degrees C. from an "idealized" steam temperature. This "idealized" steam temperature is shown to depend primarily on the maximum permissible uranium temperature. The minimum available condenser temperature and the temperature rise of the coolant in the pile effect the selection of the turbine steam temperature to lesser extent.
Date: November 16, 1953
Creator: Altmann, Manfred.
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
Physical Properties of Neutralized Zirflex Waste (open access)

Physical Properties of Neutralized Zirflex Waste

Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.
Date: June 8, 1959
Creator: Amos, L. C.
System: The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3 (open access)

Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
System: The UNT Digital Library
Fuels Preparation Department Analytical Laboratory Manual (open access)

Fuels Preparation Department Analytical Laboratory Manual

The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.
Date: June 1959
Creator: Analytical Laboratory Manufacturing Operation
System: The UNT Digital Library
Comments on Equipment for a PRTR Water Quality Control Laboratory (open access)

Comments on Equipment for a PRTR Water Quality Control Laboratory

This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
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
Steady State Temperature Distributions in Hollow Slugs (open access)

Steady State Temperature Distributions in Hollow Slugs

This document is a sequel to HW-30226, "Steady State Temperature Distribution in a Solid Slug." A primary feature of the present as well as the former paper is a treatment of the stand heat flow equation in a manner which accounts accurately for the dependence of the thermal conductivity, K, on temperature, v.
Date: December 31, 1953
Creator: Anselone, P. M.; Banks, D. O. & Dean, R. Y.
System: The UNT Digital Library
Heat Flow Problems with Temperature Dependent Thermal Conductivity (open access)

Heat Flow Problems with Temperature Dependent Thermal Conductivity

Various non-linear calculations for heat conduction in an istropic, homogeneous medium are presented.
Date: December 10, 1953
Creator: Anselone, Philip M.; Banks, D. O. & Dean, R. Y.
System: The UNT Digital Library