Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model (open access)

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
System: The UNT Digital Library
6144-Channel Time-of-Flight Analyzer (open access)

6144-Channel Time-of-Flight Analyzer

Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
System: The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column (open access)

Analog Computer Simulation of a Pulsed Extraction Column

Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
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
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: September, 1959 Through August, 1960 (open access)

Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: September, 1959 Through August, 1960

Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date: September 16, 1960
Creator: Scott, P. A.
System: The UNT Digital Library
Thermal Conductivity of UO2 (open access)

Thermal Conductivity of UO2

Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date: September 1962
Creator: Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
System: The UNT Digital Library
Portable Radiation Survey Instrument (open access)

Portable Radiation Survey Instrument

Report describing a portable radiation survey instrument, its design, and usage.
Date: September 1963
Creator: Sheen, E. M. & Spear, W. G.
System: The UNT Digital Library
The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2 (open access)

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
System: The UNT Digital Library
Surface Dosimetry and Effective Energy Calculations (open access)

Surface Dosimetry and Effective Energy Calculations

Methods of the Radiation Monitoring Operation of the Chemical Processing Department.
Date: September 8, 1956
Creator: Helgeson, G. L.
System: The UNT Digital Library
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule (open access)

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
System: The UNT Digital Library
The Identification and Determination of Trace Amounts of Rare Earth Elements in Graphite by Neutron Activation (open access)

The Identification and Determination of Trace Amounts of Rare Earth Elements in Graphite by Neutron Activation

Abstract: "A method is described for the identification and quantitative determination of trace amounts of rare earths in graphite by measurement of the energies and decays of the activities induced by neutron irradiation. The specific rare earth elements identified are europium and samarium. During the development of this method, the half-lives of Eu-152 and Sm-153 were determined. These are reported as 9.32 +/- 0.04 hours and 46.34 +/- 0.23 respectively."
Date: September 1, 1949
Creator: Ross, A. M.
System: The UNT Digital Library
Life of Van Stone Corrective Measures (open access)

Life of Van Stone Corrective Measures

This report is a document summarizing all information available on life aspects of various measures proposed to reduce or eliminate corrosion of Van Stone flanger.
Date: September 12, 1949
Creator: Botsford, C. W. & Eschbach, E. A.
System: The UNT Digital Library
Boron stainless steel for drop rods (open access)

Boron stainless steel for drop rods

From introduction: "The present investigation of the properties of boron stainless steel is an outgrowth of a project started in 1947. The problem is to replace the present steel used for drop rods in the Hanford piles with a material much less subject to corrosive attack from the humid atmosphere existing at the location of the rods."
Date: September 7, 1948
Creator: Callen, A. C. & Heckman, A. L.
System: The UNT Digital Library
Metallurgical Evaluation of the Uranium Rods Rolled for the Chalk River Pile Test (open access)

Metallurgical Evaluation of the Uranium Rods Rolled for the Chalk River Pile Test

Summary: "The laboratory data collected during the metallurgical evaluation of these rods indicate that lower rolling temperatures increased the ultimate and yield strength, the amount of cold work, and the degree of preferred orientation existing in these uranium rods."
Date: September 11, 1952
Creator: Sanderson, M. J. & Hueschen, R. E.
System: The UNT Digital Library
Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs (open access)

Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs

Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."
Date: September 11, 1952
Creator: Erkman, John O.
System: The UNT Digital Library
Autoclaving of Anodized Slug Jackets (open access)

Autoclaving of Anodized Slug Jackets

The purpose of the test used to make this report was to determine if anodizing could become a part of the canning operation prior to autoclaving, other factors permitting, or if it must follow autoclaving.
Date: September 16, 1952
Creator: Dalrymple, R. S.
System: The UNT Digital Library
Heating in the Graphite Due to a Cadmium Control Rod (open access)

Heating in the Graphite Due to a Cadmium Control Rod

From introduction: "This paper employs a multigroup method similar to that of J. S. Story, AERE-TR-177 to calculate, for cylindrical geometry, that heat energy source density in graphite due to absorption and Compton scattering of those gammas produced by neutron capture in a water filled cadmium control rod."
Date: September 29, 1951
Creator: Newkirk, W. H.
System: The UNT Digital Library
RDA-DC-4 : Engineering Study No. 6 : Protection of Exterior Buried Waste Lines (open access)

RDA-DC-4 : Engineering Study No. 6 : Protection of Exterior Buried Waste Lines

Report discussing waste line methods for separation plants at Hanford Works. A discussion of existing and proposed methods, including methods of protection for lines are included.
Date: September 24, 1952
Creator: Udine, G. U.
System: The UNT Digital Library
The Reactions of Hexone in the Redox Process (open access)

The Reactions of Hexone in the Redox Process

Report discussing several reactions that occur during the Redox process and involve hexone. Discussion of each reaction and experimental data is included.
Date: September 1, 1950
Creator: Jones, B. R. & Burger, L. L.
System: The UNT Digital Library
Decontamination of Redox Feed Solutions by Super Filtrol Scavenging (open access)

Decontamination of Redox Feed Solutions by Super Filtrol Scavenging

This report investigates multiple scavengings using Super Filtrol as a scavenging agent for removing zirconium and niobium from Hanford dissolver solution.
Date: September 1, 1950
Creator: Roake, W. E. & Hicks, H. G.
System: The UNT Digital Library
An Infrared Absorption Method for TBP After Extraction from an Aqueous Phase (open access)

An Infrared Absorption Method for TBP After Extraction from an Aqueous Phase

This report describes an improved infrared absorption method to analyze aqueous samples and TBP after extraction. The method described in the following pages is the carbon tetrachloride extraction method.
Date: September 20, 1951
Creator: Moore, R. H. & Brite, D. W.
System: The UNT Digital Library
Physical Properties of Tributylphosphate-Diluent Solutions (open access)

Physical Properties of Tributylphosphate-Diluent Solutions

In connection with the study of aqueous-tributyIphosphate (TBP) systems, the study of the interactions of various diluents with the TBP has been extended. The diluents used were mineral oil, Amsco 125-90W, dodecane, n-hexane, cyclohexane, benzene, n-octyl bromide, carbon tetrachloride, chloroform and pentachloroethane. The solubility of TBP in water from solutions of these diluents and the solubility of water in the organic phase was determined. For the paraffin hydrocarbons as diluents the solubility of TBP in water was found to increase with increasing molal volume of the diluent. No evidence for the formation of TBP-water complex of simple mole ration was found.
Date: September 1, 1953
Creator: Johnson, W. F. & Dillon, R. L.
System: The UNT Digital Library
Abrasive Cutting of Irradiated Uranium (open access)

Abrasive Cutting of Irradiated Uranium

The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.
Date: September 17, 1953
Creator: Boyd, Carl L.
System: The UNT Digital Library
Comparison of Descaling Solutions for Aluminum Alloys (open access)

Comparison of Descaling Solutions for Aluminum Alloys

A laboratory test was performed to determine if a 10% oxalic acid solution could be safely be employed as a substitute to 2% chromic acid plus 5% phosphoric acid for removal of corrosion products from aluminum corrosion samples or slugs.
Date: September 2, 1953
Creator: Dairymple, R. S.
System: The UNT Digital Library