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Fiscal Year 2005
4
ARM Facilities Newsletter
3
Enhancement of Equilibrium Shift in Dehydrogenation Reactions Using a Novel Membrane Reactor Semi-Annual Report
2
Winter Fuels Report
2
Advanced, Soluble Hydroliquefaction and Hydrotreating Catalysts Annual Report
1
Application of Reservoir Characterization and Advanced Technology to Improve Recovery and Economics in a Lower Quality Shallow Shelf San Andres Reservoir Progress Report
1
Dense Media Cyclone Optimization Progress Report
1
Fiscal Year 1998
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Fiscal Year 2006
1
Fiscal Year 2010
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Hanford Engineer Works Project 9536: C.M.X., Bldg. 145 weekly report, November 28, 1943--December 4, 1943
This report details activities of Hanford Engineer Works on Project 9536 during the week ending December, 1943. Tests are described which were run to determine means of eliminating the film which has been forming on tubes and slugs and causing excessive pressure drops.
Date:
December 9, 1943
Creator:
Kidder, C. P. & Hunt, F. L.
Object Type:
Report
System:
The UNT Digital Library
Turbidity Flocculation in Columbia River Water
This document contains data about the Columbia River water acquired January 9, 1944. The discussion includes: laboratory tests for turbidity and flocculation with aluminum.
Date:
January 9, 1944
Creator:
Frank, R. D. & Conley, W. R.
Object Type:
Report
System:
The UNT Digital Library
Reduction of size of water passages by thermal expansion: W pile
None
Date:
May 9, 1944
Creator:
Drew, T. B. & Woods, W. K.
Object Type:
Report
System:
The UNT Digital Library
Canning procedure study drop out temperature
None
Date:
June 9, 1944
Creator:
Jones, K.G.
Object Type:
Report
System:
The UNT Digital Library
Hanford Engineer Works technical progress letter No. 9, September 1 through September 7, 1944
This report details technical activities of the Hanford Engineer Works for the time period of September 1 through September 7, 1944.
Date:
September 9, 1944
Creator:
Bugbee, S. J.
Object Type:
Report
System:
The UNT Digital Library
Radiation hazards
This report is a discussion between Dr, Robert Stone of Knoxville, Tennessee and Dr. W.D. Norwood, the Medical Superintendent at HAPO, concerning the health hazards involved from working at HAPO and the maximum exposure to gamma radiation which a worker could be exposed to without receiving adverse irreparable damage. (CBS)
Date:
September 9, 1944
Creator:
Norwood, W. D.
Object Type:
Report
System:
The UNT Digital Library
Review of water supply, induced activities, and water monitoring in 100-B Area
None
Date:
September 9, 1944
Creator:
Hall, J.H.
Object Type:
Report
System:
The UNT Digital Library
Cooling water requirements in 212 buildings
This document provides plots of expected rates of heat evolution rates of heat evolution from irradiated metal which may be useful in estimating the cooling water flow required in the the 212 buildings. A comparison of three sources of data found in the Project Handbook is provided. The CN 526 calculations agree very well with the estimates of 16, 32 and 64 days decay periods. CN 526 information was used for calculating the heat evolution rates shown in the following figures, since the data does not cover decay periods under 16 days, and does not include the 93{sup 239} contribution. The expected BTU/Min.(Ton) heat liberation rate vs. cooling time in days for through operating periods is shown. The operating level is taken as 2000 KW/Ton; the BTU/Min.(Ton) liberated may be scaled to higher or lower operating levels by arithmetic ratio. A similar curve in which the cooling water required (GPM/Ton) is substituted for BTU/Min.(Ton) is provided. The metric ton and a water temperature rise of 25{degree}C (45{degree}F) are assumed. The product content of the metal has been substituted for operating level in another plot. The rate of heat evolution is plotted against decay period for various operating times. A base …
Date:
November 9, 1944
Creator:
Peery, L.C.
Object Type:
Report
System:
The UNT Digital Library
The Direct Pouring of Liquid Metal from the Reduction Bomb
By the time regular crude biscuit production was interrupted at Ames on November 9, 1944, we had made well over 100 special experimental castings by pouring the liquid metal directly from the bomb. The workmen on the regular crude production line were alternating these special castings with the regular runs without the assistance of the research group. The process had reached a state of development 'wherein the castings were made by pouring batches of about 135 pounds of liquid metal directly from the bomb into a water-cooled steel mold in the presence of air at atmospheric pressure. The pouring operation was effected through a mechanically operated valve in the bottom of the bomb. The workability of such a process has been well established, and the quality of the metal has been proved through candling and chemical tests. The first sixty billets produced by this method have been extruded successfully. A number of changes, designed to improve the quality and yield of the product and to simplify the process, have been made since producing the metal for these tests. The first set-up to test the possibility of pouring the metal directly from the bomb was made on a small scale here …
Date:
March 9, 1945
Creator:
Wilhelm, H. A.
Object Type:
Report
System:
The UNT Digital Library
Separations process batch size
A maximum batch size of 400 g Pu-239 is favored. The upper safe limit of product batch size is over 1 kg.
Date:
June 9, 1945
Creator:
Mackey, B. H.
Object Type:
Report
System:
The UNT Digital Library
Pile power level
A memorandum prepared by the Technical Department discussing the technical considerations involved in raising Pile power above the present level of 280 M.W. was discussed. A meeting attended by W. O. Simon, B. H. Mackey, L. Squires, H. Worthington, C. N. Gross, W. E. Jordan and M. H. Smith. The details of this memorandum were reviewed and the plan proposed for operation of the piles subsequent to August 1, 1945 is discussed in this report.
Date:
July 9, 1945
Creator:
Smith, M. H.
Object Type:
Report
System:
The UNT Digital Library
Technical Department report on production test No. 313-78-M: Study for evaluation of slug dimensions
The present system of classifying slugs intended for canning provides for individual measurement of dimensions on first-run MZ material, but not for their individual weighing. While the total and average weights of this type of material are determined on batches of twenty, this operation is for purposes of accounting only, and no concern is normally attached to the functional aspects of varying weights. It is thought desirable to obtain information relative to this problem. Collection of such information constitutes one of the purposes of the present test. Other purposes include collection of information which will aid in: Evaluating the improvement in overall yield brought about by adoption of the MZ diameter slugs; establishment of more suitable minimum diameter limits for recovered slugs if the present ones prove unsatisfactory; and setting up inspection procedures, if indicated, to cover measurement of dimensions as well as of weights of recovered slugs. This report provides results of this test.
Date:
July 9, 1946
Creator:
Smith, E. A.
Object Type:
Report
System:
The UNT Digital Library
100 Areas: (For Technical Progress Letter No. 109), July 30--August 5
None
Date:
August 9, 1946
Creator:
Jordan, W. E.
Object Type:
Report
System:
The UNT Digital Library
100 Areas technical activities report - physics, September 1946
The Pine unit was down four times during the month. These were all regularly scheduled shutdowns. Times down vary from 16.9 hours to 19.2 hours. A total of 33.4 tons of metal was discharged. The galvano-meter chamber in experimental hole {open_quotes}A{close_quotes} was replaced. One Special Request was discharged and three tubes have been loaded with Special Request samples. A new bismuth column has been established. Some difficulty has been experienced with high temperatures of both tube exit water and graphite following startup. On one occasion the normal operating level was exceeded for a short period of time.
Date:
October 9, 1946
Creator:
Montgomery, E. B.
Object Type:
Report
System:
The UNT Digital Library
234-5 Project, Specification Letter 234-6, 235-6, Revision 1, Waste disposal
This report outlines the general requirements for disposal of wastes from the 234-5 Buildings during the 234-5 Project.
Date:
December 9, 1947
Creator:
Work, J. B.
Object Type:
Report
System:
The UNT Digital Library
234-5 project, specification letter 234-7, 235-7, essential material storage & process solution preparation
This document presents details about the specification for space and equipment requirements for essential material storage and process solution preparation for the 234-5 project.
Date:
December 9, 1947
Creator:
Work, J.B.
Object Type:
Report
System:
The UNT Digital Library
Loss of Radioactivity from Barium Carbonate Samples
The exchange loss of radioactivity from solid samplos of barium carbonate through the agency of carbonic acid and its ions has been investigated under a variety of conditions. It is concluded that the losses observed are greatly dependent upon the method of sample preparation, in particular the nature or any heat treatment which the sample materials undergo.
Date:
January 9, 1948
Creator:
Yankwich, Peter E.
Object Type:
Report
System:
The UNT Digital Library
A new device for filtering hydrofluoric acid and other strong acids. Information report
During the course of a research problem involving hydrofluoric acid it became necessary to filter concentrated hydrofluoric solutions to remove various solid materials. The search for a suitable filter media finally led to the use of a commercially manufactured plastic material known as ``Sponge Teflon`` (polytetrafluoroethylone) which is produced by the DuPont Company. This material, which comes in 1/8 in. sheets, is used primarily as a gasket material in acid lines, and is impervious to all acids, including hydrofluorle acid.
Date:
July 9, 1948
Creator:
Bell, R.
Object Type:
Report
System:
The UNT Digital Library
Turbulent Diffusion Pattern of Turbojet Exhaust
None
Date:
September 9, 1948
Creator:
Cooley, W. C.
Object Type:
Report
System:
The UNT Digital Library
Density of metallic polonium (Information Meeting Paper No. 13)
This document is the report from a November 1948 meeting at Mound Laboratory on the measurement of the density of metallic polonium. Four determinations of the density of Polonium at 25 degrees C have been made. These values are 8.69 gm/cc, 9,34 gm/cc (twice) and 9.20 gm/cc. The probable error was 2%. The material used in the first determination was not subjected to a preliminary purification, which makes the value obtained doubtful. In this instance, production foils were used without a separation from their more volatile constituents. The difference in the reported value from that which appears in the Ad Interim Report is due to a recalculation based on the latest information on the physical constants of polonium. The value of using pure material and knowing the physical properties of polonium are clearly indicated.
Date:
November 9, 1948
Creator:
Haring, M. M.
Object Type:
Report
System:
The UNT Digital Library
Proposed radiobiological: Ecological survey of the Columbia River
None
Date:
February 9, 1949
Creator:
Foster, R. F.
Object Type:
Report
System:
The UNT Digital Library
Recommendations for separations processes program
Many questions have been raised concerning the advisability of continuing the presently scheduled Redox design and construction program in performance to other uranium recovery processes. In order to answer these questions properly, an extensive re-examination of the Redox process objectives and status and a careful study of other possible alternative uranium recovery processes have been carried out by the Hanford Works. This survey has included consideration of both existing process and facilities for plutonium separations, the Redox process, the Carbide and Carbon Uranyl Ammonium Phosphate process, uranium solvent extraction alone, and various combinations and couplings of parts or entities of the above. Comparative evaluation has been based on the relative assurance of obtaining both plutonium and uranium production; recovery of both ``aged`` and ``current`` metal wastes; timing for developing, design, and construction; economics of capital investment and operating costs; and process complexity, adaptability, and safety. This survey has resulted in conclusions and recommendations for a unified program of separations process development, design, and construction. It is the purpose of this letter to present these conclusions and recommendations, together with a brief summary of the reasons leading to their establishment.
Date:
March 9, 1949
Creator:
Greninger, A. B. & Gross, C. N.
Object Type:
Report
System:
The UNT Digital Library
Resistivity of polonium (Ad Interim)
Apparatus for measuring the resistivity of polonium is described. This equipment has been built and tested. No resistivity measurements were made, however, because the method of determining the purity of the sample has not been perfected.
Date:
March 9, 1949
Creator:
Haring, M. M.
Object Type:
Report
System:
The UNT Digital Library
Redox Committee: Conference notes and recommendations, meeting of June 9, 1949
The report includes recommendations on flow sketches; 68% nitric acid specifications; dissolver off-gas and ventilation air treatment; installation of standby equipment (details included in Appendix A); schedule of scope drawing specifications and arrangement drawings; mechanical development program (details included in Appendix B); and scope of work on waste disposal facilities (Appendix C).
Date:
June 9, 1949
Creator:
Greager, O. H.; MacCready, W. K. & Seckendorff, E. W.
Object Type:
Report
System:
The UNT Digital Library