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20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962
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.
System:
The UNT Digital Library
Data Book: Physical Properties and Flow Characteristics of Air
Data book to used as an aid in calculations on physical properties and flow characteristics of air.
Date:
March 1960
Creator:
Hobbs, J. L. & Lapides, Melvin E.
System:
The UNT Digital Library
Enrico Fermi Atomic Power Plant
Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.
Date:
March 1960
Creator:
Atomic Power Development Associates
System:
The UNT Digital Library
Evaluation of Irradiated OMRE Fuel Elements First Core Loading
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.
System:
The UNT Digital Library
Fast Reactor Core Design Parameter Study
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
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
Heavy-Water-Moderated Power Reactors: a Status Report
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
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Induction Welding for Remote Maintenance -- Final Report
Report concerning the technical feasibility of induction welding for use in remote maintenance at the Liquid Metal Fuel Reactor Experiment. Includes descriptions of the device used, test procedures, and results.
Date:
March 1960
Creator:
Dean, D. E.
System:
The UNT Digital Library
Manual of Radiation Protection Standards
"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
System:
The UNT Digital Library
Neutron Diffusion Theory Programs and Their Application to Simple Critical Systems
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-independent neutron diffusion theory criticality codes are 9ZOOM, a one-dimensional multigroup program; and 9ANGIE, a two-dimensional multigroup program. A series of codes, named SOPHIST, are described which prepare neutronic input data for the criticality codes. Examples of modification of the data to account for disadvantage factors, anisotropic scattering and for the (n,2n) reaction of Be9 are given. The critical assemblies include bare and graphite-reflected systems, using atomic BeO/U235 ratios from 247/1 to 7660/1, arranged in simple one- and two-dimensional rectangular parallelepiped arrays. All of the assemblies utilized heterogeneous arrangements of moderator and thin uranium foils. These systems are not truly thermal and are in a range where critical mass is extremely sensitive to size. The constants used in the multigroup (18 energy groups were used) calculations are presented in tabular …
Date:
March 1960
Creator:
Stone, Stuart P. & Lingenfelter, Richard E.
System:
The UNT Digital Library
PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959
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.
System:
The UNT Digital Library
Properties of High-Temperature Ceramics and Cermets: Elasticity and Density at Room Temperature
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.
System:
The UNT Digital Library
Strontium 90 Power Project: Final Summary Report
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
Creator:
unknown
System:
The UNT Digital Library
A Study of the Wear and Galling of Various Fuel Element Support Materials on Autoclaved Zircaloy-2 Interim Report No. 2
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 maintain. It also showed that metals softer than Zircaloy-2 do not scratch the process tube but that loss of these metals by abrasion into the reactor coolant might be a problem.
Date:
March 1, 1960
Creator:
Weber, J. W.
System:
The UNT Digital Library
Tory II-A Instrumentation System : Brief 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 the test bunker and transmitted by cable to the control point. The kinds of quantities measures include neutron flux level, temperatures, pressures, vibration amplitudes, strain and air mass flow rate. The recording and indicating system is centered around 258 channels of 1.5 cycle per second, pulse-width modulation tape recording equipment and 72 channels of 120 cps, analogue strip-chart records. In addition, there is a number of the usual meters, scalers and slow-response strip-chart recorders.
Date:
March 3, 1960
Creator:
Barnett, Charles S.; McDonald, Henry C. & Uthe, Paul M.
System:
The UNT Digital Library
Multi-Purpose Dissolver Information Manual
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.
System:
The UNT Digital Library
An Experimental Gamma Irradiator for Hospital Sterilization
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.
System:
The UNT Digital Library
100-N Decontamination Facility Design Guide.
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.
System:
The UNT Digital Library
Critical Pressure Ratio for a Nozzle with Two-Phase Fog Flow
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 ratios directly.
Date:
March 8, 1960
Creator:
Love, W. J.
System:
The UNT Digital Library
Glove Box Integrity Study
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 attributable to each item, would provide a basis for analyzing glove box ventilation problems and for establishing criteria for new glove box designs.
Date:
March 8, 1960
Creator:
Ciccarelli, R. A.
System:
The UNT Digital Library
Preliminary Evaluation of Chlorine for Use as a Gas Cooled Reactor Safeguard*
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 reaction. Throughout this study, a small amount of chlorine in an air stream has demonstrated the ability to substantially reduce the oxidation rate of graphite. This has been the case even where the principal oxidizing agent was molecular oxygen or ozone.
Date:
March 8, 1960
Creator:
Dahl, R. E.
System:
The UNT Digital Library
The Blast Cleaning Process as an Aid to Visual Weld Inspection
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.
System:
The UNT Digital Library
The Preparation of Plutonium Powder by a Hydriding Process--Initial Studies
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.
System:
The UNT Digital Library
Development of a Welding Process for Spire-Can Fuel Elements
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.
System:
The UNT Digital Library