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Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date:
July 18, 1960
Creator:
Frederick, C. L. & Waldkoetter, G. L.
System:
The UNT Digital Library
Hanford Controlled Potential Coulometer
Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date:
July 11, 1960
Creator:
Connally, R. E. & Scott, F. A.
System:
The UNT Digital Library
The RBU Reactor-Burnup Code: Formulation and Operation Procedures
Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date:
July 1961
Creator:
Triplett, J. R.; Merrill, E. T. & Burr, J. R.
System:
The UNT Digital Library
MINIMIZER: A Computer Code for Determining Minimum Fuel Cost
Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Date:
July 1965
Creator:
Eschbach, E. A.; Deonigi, D. E. & McConiga, A. F.
System:
The UNT Digital Library
The Hanford Isotopes Production Plant Engineering Study
Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date:
July 1963
Creator:
La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
System:
The UNT Digital Library
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Date:
July 1963
Creator:
Jackson, C. N., Jr.
System:
The UNT Digital Library
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes
Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date:
July 30, 1963
Creator:
Pessl, H. J.
System:
The UNT Digital Library
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study
Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Date:
July 1964
Creator:
Godfrey, W. L. & Benham, 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
Joint Design for Making Root Pass Welds without Filler Material
Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.
Date:
July 9, 1956
Creator:
Lemon, L. C. & Smith, W. R.
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
Program Study Report Plutonium Fuel Cycle
From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date:
July 30, 1956
Creator:
Albaugh, F. W. & Fryar, R. M.
System:
The UNT Digital Library
Standardization and Evaluation of Grain Size Test for Uranium Fuel
Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.
Date:
July 1964
Creator:
Spice, R. D.
System:
The UNT Digital Library
Urine Analysis for Tritium Oxide
This report analyzes a procedure based on the production of acetylene from the active water, with subsequent measurement of the ionization caused by the tritium beta particle. This eliminates the troublesome absorption on the chamber walls when hydrogen is used, and provides a rapid method for the preparation of the urine samples.
Date:
July 27, 1949
Creator:
Healy, J. W.
System:
The UNT Digital Library
Rate of Burnout of Absorbers
Report discussing change in absorptivity of some rare earth elements over time.
Date:
July 19, 1949
Creator:
Gillette, P. R.
System:
The UNT Digital Library
Terminal report on the Radiolanthanum Laboratory
A report which intends to acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the radiolanthanum process and to define the terminal status of the design of this laboratory and its equipment.
Date:
July 21, 1950
Creator:
Figenshau, J. K.
System:
The UNT Digital Library
Redox Process Chemistry: Freezing Point Data for UNH - NH₄NO₃ - HNO₃ - H₂O Systems
Report presenting data on freezing point for UNH - NH₄NO₃ - HNO₃ - H₂O Systems. A range of concentrations of systems was used and data is presented.
Date:
July 7, 1948
Creator:
Harmon, M. K. & Cooper, V. R.
System:
The UNT Digital Library
Analytical procedures for the plutonium Metal Fabrication Process
Report describing the results of the cupferron extraction-copper spark method in determining the impurity elements in plutonium metal. This was required the 234-5 Project analytical program.
Date:
July 25, 1952
Creator:
Bierlein, T. K.; Kendall, L. F. & Van Tuyl, H. H.
System:
The UNT Digital Library
Water Adsorbed by Graphite at Various Relative Pressures
Summary: "The quantity of water adsorbed by graphite at various relative pressures has been determined and the data are presented in graphical and tabular form."
Date:
July 21, 1953
Creator:
Spalaris, C. N.
System:
The UNT Digital Library
Examination of Discharged Process Tubes
Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."
Date:
July 21, 1952
Creator:
Dalrymple, R. S.
System:
The UNT Digital Library
Design Considerations for a Lattice Test Pile
From abstract: "The present paper proposes a lattice test pile, (or LTP) as an alternate to the continuing program of building up and tearing down of exponential piles."
Date:
July 28, 1952
Creator:
Horning, W. A.
System:
The UNT Digital Library
Manual of Radiation Protection Standards
"The following is an alphabetical listing of terms and units in common usage at HAPO. 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:
July 1957
Creator:
General Electric Company
System:
The UNT Digital Library
Liquid-Liquid Dispersions and the Significance of the Disengaging Test
From introduction: "The purpose of this report is to summarize some of the observations on the dispersion and rate of disengaging of liquid-liquid systems and suggest some possible lines of future work."
Date:
July 10, 1952
Creator:
Burger, L. L.; Dillon, R. L. & Johnson, W. F.
System:
The UNT Digital Library
Analytical Procedures for the Plutonium Metal Fabrication Process
Report describing methods of determining trace impurities in plutonium in connection with the Metal Fabrication Process. The methods included are the cupferron extraction-copper spark method and the direct copper spark method.
Date:
July 25, 1952
Creator:
Bierlein, T. K.; Kendall, L. F. & Van Tuyl, H. H.
System:
The UNT Digital Library