Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor (open access)

Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States.
Date: April 1961
Creator: Hanford Works
System: The UNT Digital Library
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water (open access)

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Date: April 1963
Creator: Rieck, H. G. 1922-
System: The UNT Digital Library
Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964 (open access)

Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.
Date: April 27, 1965
Creator: unknown
System: The UNT Digital Library
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements (open access)

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
Date: April 1961
Creator: Koler, R. K.
System: The UNT Digital Library
Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964 (open access)

Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964

Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.
Date: April 15, 1965
Creator: Platt, A. M.
System: The UNT Digital Library
The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium (open access)

The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium

Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from each other and from fission products contained in irradiated uranium fuel elements.
Date: April 8, 1957
Creator: Irish, E. R. & Reas, W. H.
System: The UNT Digital Library
Beta-Gamma Dose Rates from U232 in U233 (open access)

Beta-Gamma Dose Rates from U232 in U233

This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
Date: April 1964
Creator: Owen, F. E.
System: The UNT Digital Library
Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices (open access)

Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."
Date: April 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
System: The UNT Digital Library
The solvent-extraction performance of small scale redox IA columns using Fenske helix packing, ammonium nitrate salting agent, and unirradiated uranium (open access)

The solvent-extraction performance of small scale redox IA columns using Fenske helix packing, ammonium nitrate salting agent, and unirradiated uranium

A report which deals with the Redox IA Column studies made in small-scale columns packed with 3/16-in. Fenske helices and using NH4NO3 salting agent.
Date: April 13, 1949
Creator: Woodfield, F. W.; Bradley, J. G.; Switzer, W. O. & Merrill, E. T.
System: The UNT Digital Library
Corrosion Tests on Carboloy in Redox Process Solutions (open access)

Corrosion Tests on Carboloy in Redox Process Solutions

Introduction: Static, total immersion corrosion tests were carried out at room temperatures with Carboloy grades 44-A, 78, 907, X-3119-A and X-3119-B in Redox process solutions (ANL, June 1, 1949 Flowsheet) 1AX, 1AF, and 1AS.
Date: April 6, 1949
Creator: Koenig, W. W.
System: The UNT Digital Library
The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling (open access)

The Critical Mass of a Spherical Reactor with Variable Intrinsic Buckling

Abstract: "The critical mass both of an untamped and water-tamped sphere with parabolic radial variation of the intrinsic buckling is calculated by a perturbation method. The result is applied to finding the minimum critical mass of plutonium in water suspension with infinite water temper; the calculations show that the minimum critical mass at constant concentration may be reduced by an amount of the order of 7.6% when the concentration of plutonium is permitted to vary throughout the suspension."
Date: April 28, 1949
Creator: Muller, G. M.
System: The UNT Digital Library
"25" Critically Consultation with J. W. Morfitt : April 3, 1950 (open access)

"25" Critically Consultation with J. W. Morfitt : April 3, 1950

Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionable material."
Date: April 3, 1950
Creator: Merrill, E. T. & Sege, G.
System: The UNT Digital Library
The Determination of Uranyl Nitrate in Pretreated Hexone by Infrared Absorption Measurements (open access)

The Determination of Uranyl Nitrate in Pretreated Hexone by Infrared Absorption Measurements

The following report examines methods to determine uranium nitrate hexahydrate on pretreated hexone in the range of 0 to 40 g./l. by infrared absorption measurements.
Date: April 20, 1950
Creator: Moore, R. H.
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
Ferrous Sulfamate Stability in the RA System (open access)

Ferrous Sulfamate Stability in the RA System

Objective: "The observations summarized in the present report were made to determine the stability of ferrous and sulfamate ions and sulfamic acid in RA Column scrub solution (RAS) and in aqueous solution comparable to the RA Column feed tee composition (RAFS). Knowledge of the stability of the reducing agent (ferrous iron) is necessary to properly plan the method of preparation and introduction of this component into the RA system and to assure dependable and reproducible performance."
Date: April 20, 1950
Creator: Clagett, Fred
System: The UNT Digital Library
The Mechanism of Carrying Pu(III) on Lanthanum Fluoride (open access)

The Mechanism of Carrying Pu(III) on Lanthanum Fluoride

From introduction: "Analytical procedures for the determination of plutonium samples from the extraction and concentration plants utilize the carrying of the hydroxylamine-reduced trivulent plutonium by coprecipitation on lanthanum fluoride. Most other plutonium procedures also take advantage of the efficient carrying on lanthanum fluoride."
Date: April 15, 1952
Creator: Ralphs, Delbert Lloyd
System: The UNT Digital Library
Temperature distribution in the concrete shield (open access)

Temperature distribution in the concrete shield

Report describing the temperature in the Brookhaven concrete shield proposed for the X reactor. The report details the methods and equations used to find the values that determined that the effect of the gun barrel assembly in cooling the concrete is negligible.
Date: April 28, 1952
Creator: Triplett, John R.
System: The UNT Digital Library
Small Source Model of a Thermal Pile (open access)

Small Source Model of a Thermal Pile

Report discussing the use of a small-source approximation for engineering calculation of thermal piles. Explanation for how this type of approximation is more appropriate in certain problematic situations where a homogenization approximation would be doubtful is given.
Date: April 30, 1952
Creator: Horning, W. A.
System: The UNT Digital Library
Final Report: Rear Face Monitoring by Television (open access)

Final Report: Rear Face Monitoring by Television

Report discussing a method of rear face monitoring by television as a form of visual contact and communication between Hanford Works crews. A conclusion and recommendation of the method is given as well as an explanation of necessary materials.
Date: April 3, 1953
Creator: Morris, W. J.
System: The UNT Digital Library
The Preparation of Samples for Hanford Works Special Irradiation Requests (open access)

The Preparation of Samples for Hanford Works Special Irradiation Requests

This report discusses the development of a method for creating leak-proof closures in aluminum sample casings in order to pass a standard bubble-test inspection.
Date: April 9, 1951
Creator: McMaster, J. V. & Johnson, H. A.
System: The UNT Digital Library
Corrosion Data for LaBour R-55 and Worthite in UO₃ Process Streams (open access)

Corrosion Data for LaBour R-55 and Worthite in UO₃ Process Streams

Introduction: "A corrosion test program, to determine the suitability of LaBour B-55 and Worthite for use in the construction of circulating pumps for th UO3 process has been completed and the data are appended."
Date: April 4, 1951
Creator: Sanborn, K. L.
System: The UNT Digital Library
Corrosion Tests on Stainless Steel Plate-Waste Metal Recovery Process (open access)

Corrosion Tests on Stainless Steel Plate-Waste Metal Recovery Process

Introduction: A limited test progress on Alloghany-Ludlum type 347 stainless steel plate which failed the Huey test (ASTN A-262-44T) has been completed.
Date: April 9, 1951
Creator: Sanborn, L.
System: The UNT Digital Library
Radioactive Particles in the Atmosphere : January 1951 - March 1951 (open access)

Radioactive Particles in the Atmosphere : January 1951 - March 1951

Report discussing studies regarding active atmospheric particles in several United States cities. Experimental data of particles collected in filters is given.
Date: April 12, 1951
Creator: Singlevich, W.
System: The UNT Digital Library
Quarterly Progress Report: Research and Development Activities for January - March, 1951 (open access)

Quarterly Progress Report: Research and Development Activities for January - March, 1951

Report discussing progress in research and development by the Health Instrument Divisions, Hanford Works, for the term from January through March, 1951.
Date: April 18, 1951
Creator: Parker, H. M.
System: The UNT Digital Library