Resource Type
Collection
Serial/Series Title
HW (Series)
4
Hanford Works Reports
4
Atomic Energy Commission Reports
2
Oak Ridge National Laboratory Reports
2
University of California Radiation Laboratory Reports
2
AEC research and development report
1
AECU (Series)
1
Armour Research Foundation Reports
1
GEAP (Series)
1
General Electric Company Atomic Power Reports
1
5 More
Country
Year
Day
21 Matching Results
Results open in a new window/tab.
Results:
1 - 21 of
21
Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System
Abstract: "The niobium-carbon system has been determined by X-ray and metallographic examination of sintered and arc-cast alloys. Two carbides exist: hexagonal Nb2C with a limited range of homogeneity, and cubic NbC with a solubility range from 8.25 to 10.25 weight per cent carbon. Dilute alloys freeze by eutectic reaction at 2230 C. The solubility of carbon in niobium is 0.80 at the eutectic temperature, but this decreases rapidly with temperature. Metallographic evidence indicates a peritectic reaction between melt, Nb2C, and NbC; alloys richer in carbon than NbC freeze by eutectic reaction."
Date:
May 6, 1959
Creator:
Elliott, Rodney P.
System:
The UNT Digital Library
Definitive process design, Redox multi-purpose dissolver installation
This document provides the required definitive scope design for dissolver equipment capable of nuclear safe processing by geometry of E-Metal and certain other fuels enriched to a maximum of one per cent U-235 equivalent. Using only a single dissolver installation of this design, it will be possible to process the current E-Metal monthly commitment in less than two weeks (five-day week). The proposed dissolver system is to incorporate design flexibility required to permit conversion to Zirflex processing of NPR fuels.
Date:
May 6, 1959
Creator:
Gustafson, L. D.
System:
The UNT Digital Library
Study of Electric Propulsion Systems for Space Travel: Interim Progress Report for July 1 to December 31, 1958
Report discussing the progress made on a study of electric propulsion for space travel during the period from July 1, 1958 to December 31, 1958 at the Lawrence Radiation Laboratory in Livermore, California.
Date:
February 6, 1959
Creator:
Fox, Robert H.
System:
The UNT Digital Library
Interim report on laboratory experiments investigating consequences of failure of front hydraulic fittings in ``C`` OCD geometry
None
Date:
May 6, 1959
Creator:
Fitzsimmons, D. E. & Hesson, G. M.
System:
The UNT Digital Library
Irradiation summary -- PT-IP-179-A-97-FP: Evaluation of the effect of a modified Beta-Heat treatment cycle on dimensional stability of uranium fuel elements
The air quench prior to water quench during core heat treatment can be used to control slug distortion. In August 1959, a production test authorized the charging of 16 tubes of 43-second air quench material alternated with standard control material in C-Reactor. The test was charged on November 24, 1958, and discharged on April 26, 1959. This report summarizes and evaluates the irradiation performance of the material.
Date:
August 6, 1959
Creator:
Peacock, D. W. & Hall, R. E.
System:
The UNT Digital Library
Fringe isotope production
The Purpose of the work described in this report has been to determine experimentally the rate of production of tritiun in fringe lithium-aluminum alloy loadings with the degree of precision necessary for economic analyses of such a method of isotope production. These results are provided for use in such an analysis.
Date:
May 6, 1959
Creator:
Bunch, W. L.
System:
The UNT Digital Library
A Large Bakeable Vacuum Valve
This report describes the development and design of a large bakeable valve that is based on a unique seat arrangement and a novel motion seal.
Date:
August 6, 1959
Creator:
Batzer, Thomas H.
System:
The UNT Digital Library
Hazards Summary Report for the Walter Reed Army Medical Center Nuclear Research Reactor
Detailed descriptions are given concerning the reactor design, operation, location, and the using agency. Potential hazards are evaluated along with safeguards. A supplement is included which further describes the reactor core. (J.R.D.)
Date:
May 6, 1959
Creator:
Cappel, H.H.
System:
The UNT Digital Library
[Imperial Sugar Company Actual and Projected Operations: 1959]
Monthly report documenting Imperial Sugar operational expenses for the year, broken down by actual sales and production, with estimated operational numbers for the remainder of the year.
Date:
January 6, 1959
Creator:
Imperial Sugar Company
System:
The Portal to Texas History
Oak Ridge National Laboratory Status and Progress Report September 1959
None
Date:
October 6, 1959
Creator:
unknown
System:
The UNT Digital Library
The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions
Preliminary measurements of the corrosion of titanium were made in 13 M HNO3-0.05 M fluoride using 0.1 M H3BO3 as a liquid and vapor phase complexing agent. Titanium Ax-55 was attacked at average rates of 0.58 and 0.33 mils/month in the liquid and vapor. In dissolver solutions containing 0.5 and 1.0 M titanium, all rates were less than 0.1 mils/month.
Date:
August 6, 1959
Creator:
Kitts, F. G.
System:
The UNT Digital Library
Texas S-R Suspensions by County: 1958
Annual report providing tabular statistical information about license safety responsibility (S-R) suspensions of drivers in Texas for failure to file or show proof of financial responsibility resulting from convictions and accidents, broken down by county and by locations of out-of-state accidents. It also includes very basic overview information about filing proof of financial responsibility.
Date:
January 6, 1959
Creator:
Texas. Department of Public Safety. Statistical Services.
System:
The Portal to Texas History
Confinement System Instrumentation
Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date:
November 6, 1959
Creator:
Richards, W. A.
System:
The UNT Digital Library
Uranium deposits in the Pryor-Big Horn Mountains, Carbon County, Montana, and Big Horn County, Wyoming
Discussing the occurrence of uranium deposits in the Pryor-Bighorn Mountains.
Date:
February 6, 1959
Creator:
Hart, Olin M.
System:
The UNT Digital Library
Flow Decay After an Electrical Power Outage in the PRTR
Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date:
February 6, 1959
Creator:
Muraoka, J.
System:
The UNT Digital Library
Specification for Requisition G-3855923Xircalogy-4 Jacket Tubing
This specification is specifically designed for the procurement of Zircaloy tubing to be used in the of swaged, UO fuel elements, an, and the Pu fuel elements for the Plutonium Recycle Test Reactor. Requisition G-385923 contains the following information pertinent to this specification: 1. Dimensions and dimensional tolerance. 2. Source of zirconium sponge and conditions for us of Zircaloy scrap. 3. Inspection requirements. 4. Shipping instructions.
Date:
November 6, 1959
Creator:
Oakes, H. P.
System:
The UNT Digital Library
PRTR Hazard Analysis For Various Mechanical Failures
The hazards associated with several possible mechanical failures were analyzed for the PRTR. The consequences of these failures were evaluated for inclusion in the Final Hazards Summary Report.
Date:
July 6, 1959
Creator:
Muraoka, J.
System:
The UNT Digital Library
Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station
This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date:
February 6, 1959
Creator:
Commonwealth Edison Company
System:
The UNT Digital Library
Flame Photometric Determination of Iron Parts I, II, III and IV
A study was made of a method for the flame photometric determination of iron. In Part I of this report, the flame emission spectrum of iron, measured by means of a Beckman Model DU spectrophotometer with a flame attachment, is compated to that measured with an ORNL high-sensitivity, recording, single-beam instrument, in order to determine which instrument is best suited for this application. Although it was found that the Beckman product has the higher resolving power over the wavelength region of 360 to 400mu, it does no posses the sensitivity or ease of operation of the ORNL instrument. On this basis, the ORNL flame spectrophotometer is used in subsequent tests. After selecting the best-suited instrument for the flame photometric determination of iron, it was necessary to establish the optimum operating conditions for this particular method. These conditions are described in Part II.
Date:
May 6, 1959
Creator:
Menis, Oscar
System:
The UNT Digital Library
Dynamic Response of Reactor Plant to Load Changes. Section I. First Performance. Core I, Seed 1. Test Results DL-S-251 (T-612390)
The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the the load change. The pressurizer spray was effective in reducing reactor coolant pressure positive surges; however, this resulted in larger negative surges than when the spray valve was closed.
Date:
November 6, 1959
Creator:
Gentry, George
System:
The UNT Digital Library
Preliminary Safety Analysis of the Sodium-Deuterium Reactor (SDR)
From abstract: This work is a safety analysis of the preliminary design of a nuclear reactor.
Date:
March 6, 1959
Creator:
Beusman, Curtis C. & Bernsohn, E.
System:
The UNT Digital Library