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Meeting XI Bevatron Research Conference
It will be desirable to have a general purpose bending magnet available for use with the Bevatron. The design discussed, while tentative, is believed to incorporate most of the desired properties for use with the external beam.
Date:
January 12, 1954
Creator:
Wenzel, William A.
Object Type:
Article
System:
The UNT Digital Library
PREPARATION OF CARRIER-FREE YTTRIUM-90. (INFORMATION REPORT)
None
Date:
February 12, 1954
Creator:
Salutsky, M.L. & Kirby, H.W.
Object Type:
Report
System:
The UNT Digital Library
Process Test MR-105-23 cathodic protection of the 107-C retention basins
This report provides details of a test to determine the feasibility of preventing corrosion of the 107- C retention basins by the installation of a small scale cathodic protection system.
Date:
July 12, 1954
Creator:
Bloomstrand, R. R.
Object Type:
Report
System:
The UNT Digital Library
Radiological Sciences Department investigation, radiation incident, Class I, No. 371
During a routine beta-gamma hand and shoe count, an employee discovered that his shoes were contaminated. This document discusses the spread of particulate contamination at the Biophysics Laboratory, Building 329, 300 Area on July 6, 1954.
Date:
July 12, 1954
Creator:
Vanderbeek, J. W.
Object Type:
Report
System:
The UNT Digital Library
THE PREPARATION AND PROPERTIES OF TETRA-ALKYL-AMMONIUM BOROHYDRIDES
None
Date:
January 12, 1955
Creator:
Wallace, E.K.; Bridges, J.; Dering, J.; Dumot, J.; Eisley, N.; Hartmen, S. et al.
Object Type:
Report
System:
The UNT Digital Library
200 Area processing rates
Two types of ``feedstock,`` i.e. irradiated uranium and uranium from underground storage, are processed by the 200 Areas. Future operations may add irradiated thorium as a supplementary feed material. In either case, the major portion of future feedstocks is presumed to be in the form of irradiated metal, i.e. uranium and/or thorium, resulting in an almost complete dependence of the required 200 Area processing rate on reactor power levels and metal irradiation history. This document presents correlations by which predicted reactor power levels and production commitments for particular types of product may be easily converted to the required separations processing rates. Separations processing rates potentially resulting from low NGS plutonium and ``23`` commitments are given for the period through 1957.
Date:
April 12, 1955
Creator:
Platt, A. M.
Object Type:
Report
System:
The UNT Digital Library
Purex pulse column designs for capacity factor of 3.0 to 3.5
This memorandum indicates the Purex-Plant pulse-column and pulse- generator revisions which would be required to assure an instantaneous capacity of 25 tons U/day with a 20% capacity safety margin under Purex HW {number_sign}3 Flowsheet conditions. (The use of the Purex HW {number_sign}4 Flowsheet (6) with the revised columns would be expected to increase the capacity to 29 or 30 tons U/day.) The indicated design changes are recorded here for study and for possible reference if need for increased production capacity should arise. No recommendation for adoption at this time is made.
Date:
April 12, 1955
Creator:
Richardson, G. L.
Object Type:
Report
System:
The UNT Digital Library
Nuclear metallurgy lectures. Chapter 9, Fabrication and heat treatment of uranium
This chapter presents the highlights of the fabrication and heat treatment of uranium with emphasis on HAPO type core material. For pile use three properties of uranium are of prime interest; grain size, type and degree of preferred orientation, and the mechanical properties.
Date:
May 12, 1955
Creator:
Riches, J. W.
Object Type:
Report
System:
The UNT Digital Library
THE HYDROLYSIS OF THE COMPOUND OF POTASSIUM WITH IRRADIATED GRAPHITE
Potassium, the reaction product of graphite with potassium, and the reaction product of irradiated graphite with potassium were subjected to hydrolysis. The gases evolved from the respective samples were analyzed mass spectroscopically. Hydrocarbons (methane and a trace of ethane) were found in the gas evolved from the irradiated graphite compound only, and the quantity was about that which would have been expected from the number of non-aggregated displaced atoms. The result was obtained for a single set of experiments and must be considered suggestive rather than conclusive. (auth)
Date:
September 12, 1955
Creator:
Primak, W.L. & Quarterman, L.A.
Object Type:
Report
System:
The UNT Digital Library
IRRADIATION EXPERIMENT ON ETR BORON CONTAINING FUEL ELEMENTS
None
Date:
September 12, 1955
Creator:
Beaver, R J
Object Type:
Report
System:
The UNT Digital Library
A Purex process one cycle plant study
In keeping with the announced goals for production at Hanford, a series of separations plant studies is being conducted with the objective of providing an insight into worthwhile design development goals both process and plant-wise. These studies will provide a basis for evaluation of research and development programs, with all cost estimates and other supporting information standardized, both in presentation and detail. These developments are vital to the future of separations plant planning in order that proper emphasis be placed on the most economic production facility for HAPO, should production planning require an additional major facility. This report is the second of a series, reporting on the design developments under way. The purposes of this document are to present the results of the second separations plant design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve the significant capital and operating cost reductions indicated.
Date:
December 12, 1955
Creator:
Fecht, J. B.; Jaske, R. T.; Lane, T. V. & Ludlow, J. O.
Object Type:
Report
System:
The UNT Digital Library
Chemical Development Status Report for Week Ending March 2,1956
None
Date:
March 12, 1956
Creator:
Blanco, R. E. & Ferguson, D. E.
Object Type:
Report
System:
The UNT Digital Library
Orientation of control rods
It was recommended that the control rods in the septifoils of the reactor be reoriented in order to improve flux shaping; burnout was not mentioned. This memorandum re-examines the problem of orientation of the control rods considering not only flux shaping but also burnout.
Date:
March 12, 1956
Creator:
Babcock, D. F. & Bernath, L.
Object Type:
Report
System:
The UNT Digital Library
SPECTROGRAPHIC ANALYSIS OF TISSUES FOR TRACE ELEMENTS. Progress Report for July 1, 1955 through December 31, 1955
None
Date:
March 12, 1956
Creator:
Tipton, I H; Cook, M J; Steiner, R S; Foland, W D; Bowman, D K & McDaniel, K K
Object Type:
Report
System:
The UNT Digital Library
Air-Cooled Condenser Steam System. Hr Engineering Test Procedure v 5
None
Date:
April 12, 1956
Creator:
Gory, J. L. & Williamson, H. E.
Object Type:
Report
System:
The UNT Digital Library
Antimony-125 in Thorex Streams
This report addresses the analyses for fission-product antimony-125 made on samples of selected Thorex streams. The results are summarized in Table I
Date:
April 12, 1956
Creator:
Handley, T. H. & Reynolds, S. A.
Object Type:
Report
System:
The UNT Digital Library
Chemical development status report for week ending April 6, 1956
None
Date:
April 12, 1956
Creator:
Blanco, R. E. & Ferguson, D. E.
Object Type:
Report
System:
The UNT Digital Library
The Development of a Thermal-Neutron-Flux Measuring Instrument
None
Date:
April 12, 1956
Creator:
Smith, C. K.; Weaver, C. V.; Chastain, J. W. & Fawcett, S. L.
Object Type:
Report
System:
The UNT Digital Library
FABRICATION OF HEATER TUBE FUSES
Various methods were investigated to produce a heater tube fuse. Utilizing powder metallurgy techniques, fuel tubes with an I.D. of 0.045 inch, O.D. of 0.075 inch, and length of 11/16 inch, containing various compositions of copper + UO/sub 2/, were fabricated. Fabrication methods consisted of compacting the tubes in quarter-length units, sintering under optimunn conditions, coining on a tinplated inner tube with tin washers between units, and then heat treating to obtain a proper bond. By these techniques, 33 unis containing various compositions of copper + U/sup 235/O/sub 2/ were fabricated and shipped to Atomics International for testing. In addition, work was performed on the brazing facet of the trigger element assembly, joining the copper + UO/sub 2/ fuel tube to a type 347 stainless steel thermal resistance pad and block. (auth)
Date:
April 12, 1956
Creator:
Kalish, H. S. & Megeff, S. I.
Object Type:
Report
System:
The UNT Digital Library
The Fire Properties of Metallic Uranium
None
Date:
April 12, 1956
Creator:
Smith, R. B.
Object Type:
Report
System:
The UNT Digital Library
PHASE III FUEL SAMPLE IRRADIATION. IRRADIATION REQUEST ORNL-21
None
Date:
April 12, 1956
Creator:
Neill, F.H. & Waugh, R.C.
Object Type:
Report
System:
The UNT Digital Library
RESULTS OF PRELIMINARY NUCLEAR CALCULATIONS FOR A HOMOGENEOUS RESEARCH REACTOR
Critical mass, fuel concentration, power, maximum power density, and wall power density were obtained for bare spherical reactors having diameters of 8, 10, 11, and 12 ft, operating at 20, 100, 2OO, and 300 deg C. (L.T.W.)
Date:
April 12, 1956
Creator:
Nestor, C. W. Jr.
Object Type:
Report
System:
The UNT Digital Library
Three-Region Reflector-Moderated Critical Assembly With End Products. Experimental Results with CA-21-2. Reduced Concentration
None
Date:
April 12, 1956
Creator:
Scott, Dunlap; Lynn, J. J.; Sandin, E. V. & Snyder, Stuart
Object Type:
Report
System:
The UNT Digital Library
Nuclear Instrumentation System System Description No. 15
Modifications are described in the nuclear instrumentation system of the Shippingport Pressurized Water Reactor designed to monitor neutron flux level from source to 150% of reactor designed full power output, to compute the rate of change of the neutron flux level for indication and control, and to provide level and rate of change of level signals for reactor shutdown to prevent reactor damage. (C.H.)
Date:
May 12, 1956
Creator:
Wilson, N. E.
Object Type:
Report
System:
The UNT Digital Library