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An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date:
March 1, 1958
Creator:
Hanford Works
System:
The UNT Digital Library
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date:
June 2, 1958
Creator:
Spear, W. G.
System:
The UNT Digital Library
An Automatic Analyzing Monitor for Reactor Effluent Cooling Water
From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date:
May 1, 1959
Creator:
Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
System:
The UNT Digital Library
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
Construction Completion Report: CAI-816, 100-N Reactor Plant
Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date:
October 15, 1964
Creator:
Buckner, C. L.
System:
The UNT Digital Library
Conversion of UNH to UO3 : Terminal Report
Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.
Date:
January 10, 1951
Creator:
Maness, R. F. & Clagett, F.
System:
The UNT Digital Library
Critical Mass Studies of Plutonium Solutions
Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date:
February 15, 1960
Creator:
Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System:
The UNT Digital Library
Description of Purex Plant Process
Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date:
May 19, 1959
Creator:
Irish, E. R.
System:
The UNT Digital Library
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks
Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
Date:
May 15, 1958
Creator:
Morrow, G. W.
System:
The UNT Digital Library
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Date:
October 20, 1959
Creator:
Moore, R. H. & Lyon, W. L.
System:
The UNT Digital Library
Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor
Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.
Date:
June 17, 1954
Creator:
Paul, R. S. & Wood, M. R.
System:
The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date:
June 1961
Creator:
Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System:
The UNT Digital Library
Effect of Process Variables on Graphite Purity
Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.
Date:
July 20, 1954
Creator:
Riley, W. C. & Corners, A. M.
System:
The UNT Digital Library
The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete
Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
Date:
December 11, 1958
Creator:
Wood, D. E.
System:
The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1
Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date:
February 1961
Creator:
Pessl, H. J.
System:
The UNT Digital Library
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes
Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date:
July 31, 1959
Creator:
Knecht, R. L.
System:
The UNT Digital Library
Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date:
March 1, 1958
Creator:
Johnson, B. M.
System:
The UNT Digital Library
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
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
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date:
March 1961
Creator:
Baars, R. E.
System:
The UNT Digital Library
Final Design Report KAPL-120 High Pressure Recirculating Water Loop
Basic information on the design of the Knolls Atomic Power Laboratory (KAPL) -120 loop.
Date:
January 15, 1956
Creator:
Wade, G. E. & Berberet, J. A.
System:
The UNT Digital Library
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity
A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date:
June 26, 1959
Creator:
Jackson, P. M.
System:
The UNT Digital Library
Halogen Collector Test Program
Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
System:
The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility
A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date:
June 1961
Creator:
Muraoka, J.
System:
The UNT Digital Library