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20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962

Description: From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
Date: March 1960
Creator: Vortman, Luke J. & MacDougall, H. R.
Partner: UNT Libraries Government Documents Department
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Enrico Fermi Atomic Power Plant

Description: Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.
Date: March 1960
Creator: Atomic Power Development Associates
Partner: UNT Libraries Government Documents Department
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Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department
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Fast Reactor Core Design Parameter Study

Description: Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
Partner: UNT Libraries Government Documents Department
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Halogen Collector Test Program

Description: 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.
Partner: UNT Libraries Government Documents Department
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Heavy-Water-Moderated Power Reactors: a Status Report

Description: From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."
Date: March 1960
Creator: Babcock, Dale Friend
Partner: UNT Libraries Government Documents Department
open access

Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: March 1, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Neutron Diffusion Theory Programs and Their Application to Simple Critical Systems

Description: Introduction. The Lawrence Radiation Laboratory of the University of California has developed a series of reactor neutronic programs for an IBM 709 Data Processing System.. This paper presents a brief outline of these codes and includes the results of one- and two-dimensional diffusion calculations used to interpret data from a series of enriched-uranium beryllium-oxide moderated critical measurements. These were performed for the specific purpose of evaluating the computer programs. The time-i… more
Date: March 1960
Creator: Stone, Stuart P. & Lingenfelter, Richard E.
Partner: UNT Libraries Government Documents Department
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PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959

Description: From abstract: The principal efforts are the furthering of the final design and preparation of specifications for some long-lead components. The entire power plant has been divided, for final design purposes, into 37 subsystems. The status of work on each subsystem at the close of the period is reported.
Date: March 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Properties of High-Temperature Ceramics and Cermets: Elasticity and Density at Room Temperature

Description: From Introduction: "The present paper contains detailed descriptions of the methods used in calculating both the elastic constants and the statistical parameters. These detailed descriptions have been included for two reasons: (1) To leave no doubt as to the exact procedure, and (2) to act as a guide to other workers who might wish to make similar determinations."
Date: March 1, 1960
Creator: Lang, S. M.
Partner: UNT Libraries Government Documents Department
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Strontium 90 Power Project: Final Summary Report

Description: From summary: The primary purpose of this project is to determine the feasibility of converting reactor waste Strontium-90 into a safe and useful source of electrical energy. Secondary purpose is physical and environmental testing of the power conversion device or thermoelectric couples. This required actual fabrication of a 100-thermal-watt strontium titanate fuel element
Date: March 1960
Partner: UNT Libraries Government Documents Department
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A Study of the Wear and Galling of Various Fuel Element Support Materials on Autoclaved Zircaloy-2 Interim Report No. 2

Description: This is the second of two reports describing the phases of a study of the wear and galling of autoclaved Zircaloy-2 by various fuel element support materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 support and the autoclaved Zircaloy-2 process tube will not significantly improve the fuel support performance, and that a large flat contact area between the fuel supports and the process tube would be impractical to endeavor to achieve and maintai… more
Date: March 1, 1960
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
open access

Tory II-A Instrumentation System : Brief Description

Description: Abstract. The Tory II-A reactor is a small, air cooled, high power-density reactor which is to operate at quite high temperatures. Design of the reactor is essentially complete. First operation is scheduled for late 1960 at the Nevada Test Site of the Atomic Energy Commission. Since the reactor is unshielded, the control room which houses the recording and indicting equipment is located approximately two miles from the test bunker. Signals from reactor and facility transducers are amplified in … more
Date: March 3, 1960
Creator: Barnett, Charles S.; McDonald, Henry C. & Uthe, Paul M.
Partner: UNT Libraries Government Documents Department
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Multi-Purpose Dissolver Information Manual

Description: The multi-purpose dissolver was designed to provide: 1. A critically safe vessel for dissolving uranium metal of enrichments up to one percent U-235. 2. A vessel which can be charged with fuel elements up to 10 feet long. 3. An off-gas arrangement which will eliminate return of ammonia to the dissolver during the Zirflex decladding process. 4. A vessel in which small charges can be dissolved without using extra chemicals. 5. A by-pass routing around the silver reactor during cladding removal.
Date: March 4, 1960
Creator: Simonds, H. P.
Partner: UNT Libraries Government Documents Department
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An Experimental Gamma Irradiator for Hospital Sterilization

Description: From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date: March 7, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
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100-N Decontamination Facility Design Guide.

Description: Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date: March 8, 1960
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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Critical Pressure Ratio for a Nozzle with Two-Phase Fog Flow

Description: In many cases of analysis of two-phase flow in systems, considerable computation or program time could be saved if the critical pressures ratio were known. If a reservoir or plenum pressure is fixed, the usual computational procedure involves the assumption of several critical pressures and the generation of several momentum terms to find the applicable critical pressure ratio and thereby the critical flow. The formulation of an equation of state make it possible to compute critical pressure ra… more
Date: March 8, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Glove Box Integrity Study

Description: The amount of dry air or inert gas supplied to a "one pass" glove box ventilation system is proportional to the glove box inleakage. Most glove boxes in the 234r5 Building are equipped with sundry attachments, each contributing to the inleakage. No individual leak rate date is available for these auxiliary components in the "as installed" condition. Nor is the effect of time upon the leak rates known. Knowledge of these values, or at least an indication of the order of magnitude of the leakage … more
Date: March 8, 1960
Creator: Ciccarelli, R. A.
Partner: UNT Libraries Government Documents Department
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Preliminary Evaluation of Chlorine for Use as a Gas Cooled Reactor Safeguard*

Description: A coolant line rupture during operation of a high temperature gas cooled graphite moderated reactor would present a serious hazard. The reactor would immediately depressurize and a great deal of air would be introduced into the coolant stream. As the air passed over the graphite moderator a runaway oxidation reaction would probably ensue unless an adequate safety system were available. This investigation was designed to evaluate chlorine as a reactor safeguard to be used to control a runaway re… more
Date: March 8, 1960
Creator: Dahl, R. E.
Partner: UNT Libraries Government Documents Department
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The Blast Cleaning Process as an Aid to Visual Weld Inspection

Description: Late in 1958 it became apparent that some fuel elements were failing in the Hanford reactors as a result of water entering through the weld. The mode of entry appeared to be first through a void in the weld, then through a non-wet area or a train of voids in the braze, and finally to the uranium core. Defective closures of a similar nature were also typical of many fuel elements which have failed in the autoclaving operation as shown in Figure 1.
Date: March 9, 1960
Creator: Hanson, G. R.
Partner: UNT Libraries Government Documents Department
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The Preparation of Plutonium Powder by a Hydriding Process--Initial Studies

Description: Powder metallurgy is rapidly gaining importance as a means of fabricating nuclear fuel elements and other reactor components. It provides a convenient method for forming metals, unusual combinations of metals, and metal-ceramic combinations. The unique features of this technique which make it desirable for nuclear engineering purposes are the following:
Date: March 10, 1960
Creator: Stiffler, G. L. & Curtis, M. H.
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for Spire-Can Fuel Elements

Description: The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.
Date: March 11, 1960
Creator: Hanson, G. R.
Partner: UNT Libraries Government Documents Department
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