Resource Type
Partner
Collection
Technical Report Archive and Image Library
1,250
National Advisory Committee for Aeronautics Collection
775
Office of Scientific & Technical Information Technical Reports
326
TRAIL Microcard Collection
263
Texas State Publications
6
Harris and Eliza Kempner
4
John J. Herrera Papers
2
Texas Cultures Online
2
General Collection
2
Abilene Library Consortium
1
3 More
Serial/Series Title
NACA Research Memorandums
440
NACA Technical Notes
236
Atomic Energy Commission Reports
227
United States Geological Survey Reports
93
United States Bureau of Mines Reports
59
NACA Technical Reports
57
Hanford Works Reports
49
HW (Series)
47
Trace elements investigations report
42
ORNL (Series)
41
85 More
Degree Level
States
Dry Fluoride Process Status Report
Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [From Abstract, Summary]
Date:
March 27, 1951
Creator:
Leuse, R. E.
System:
The UNT Digital Library
Boiling Reactors: A Preliminary Investigation
Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]
Date:
December 12, 1951
Creator:
Stein, J. M. & Kasten, P. R.
System:
The UNT Digital Library
Thorium and Thorium Alloys Preliminary Corrosion Tests
Technical report investigating the corrosion resistance of thorium and thorium alloys containing from 2 to 6% chromium, columbinium (niobium), titanium, zirconium and titanium-zirconium in distilled water at 95ºC. The true effects of the various alloy additions could not be determined because of the more marked effect of cold working. [From Abstract]
Date:
December 19, 1951
Creator:
Olsen, Arnold R.
System:
The UNT Digital Library
The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process
From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."
Date:
December 13, 1951
Creator:
Reilly, V. J. & Lanham, W. B.
System:
The UNT Digital Library
Enrichment of Uranium 236
From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."
Date:
December 1951
Creator:
Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
System:
The UNT Digital Library
Enrichment of Uranium 236
From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."
Date:
December 1951
Creator:
Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
System:
The UNT Digital Library
Physics Division Quarterly Progress Report for Period Ending March 20, 1951
Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date:
July 2, 1951
Creator:
Bernstein, S.; Snell, A. H. & Wollan, E. O.
System:
The UNT Digital Library
An Investigation of ThF4 - Fused Salt Solutions for Homogeneous Breeder Reactors
Technical report presenting a consideration of the characteristics of fused salt-ThF4 solutions suitable for use in homogeneous reactors. Presented in tandem with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. [From Abstract]
Date:
June 19, 1951
Creator:
Blomeke, J. O. & Johnston, C. P.
System:
The UNT Digital Library
An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor
Technical report containing the general arrangement of the Low Intensity Training Reactor and outcomes of experiments that have been performed in the reactor to measure the rate of fission product heat dissipation from the fuel pieces after loss of water. [From Summary, Introduction]
Date:
September 25, 1951
Creator:
Beall, S. E.
System:
The UNT Digital Library
Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951
This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.
Date:
September 30, 1951
Creator:
Lind, Samuel C., (Samuel Colville), 1879-1965; Boyd, G. E. & Bredig, M. A.
System:
The UNT Digital Library
Removal of ruptured uranium slug from tube No. 4374-B
None
Date:
October 15, 1951
Creator:
Koop, W.N.
System:
The UNT Digital Library
Report of your first National Vice President
Report on LULAC activities of John J. Herrera, LULAC First National Vice-President, during the second half of 1950 and first half of 1951. Events and activities are listed in chronological order, broken down by city and event.
Date:
June 1951
Creator:
Herrera, John J.
System:
The Portal to Texas History
[Report of LULAC National Treasurer for June 24, 1951 - June 19,1952]
Report of the National Treasurer, League of United Latin American Citizens, Laredo, Texas, for Cash Receipts and Disbursements, June 24, 1951-June 19, 1952. This report was submitted by Felix Garcia, Jr., LULAC National Treasurer on June 19,1952.
Date:
June 19, 1951
Creator:
Garcia, Felix, Jr.
System:
The Portal to Texas History
Tentative design basis new 100 Area water plant embodying a close cooling water circuit
The attached document includes a plot plan, flow diagram and delineation of basic assumptions upon which the report was developed. It summarizes the work which has been accomplished to date under RDA No. DC-6 in developing a recirculating water system to serve a new reactor. In order to proceed with the work under RDA No. DC-6 it has been necessary to make certain basic assumptions relative to the primary circuit requirements of RDA No. DC-3. These assumptions are explained in the report and are presented by the exhibits contained therein. Subsequent to the compilation of the basic report certain additional considerations have come to the authors attention and are included in the addendum.
Date:
November 14, 1951
Creator:
unknown
System:
The UNT Digital Library
Vernatherm functional test, Test Project No. 14
The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error, if any, that is induced in a standard Vernatherm unit of known calibration when subjected to gamma irradiation. The accuracy of the units prior to irradiation was within 1.25 F. An examination of the calibration curves shows that a hysteresis effect in the hydrocarbon of the unit causes the curve of descending temperature to be displaced from the ascending temperature curve. The effects of irradiation were to decrease the accuracy to within 3.75 F. After a total exposure of 17,416 {times} 10{sup 4}R at 1.1 MEV. Since the exposure of 11,441 {times} 10{sup 4}R is equivalent to approximately 2,000 months exposure in the pile at 250 MW they can conclude that the effect of radiation is not detrimental since the increase in …
Date:
October 31, 1951
Creator:
Smith, J. L.
System:
The UNT Digital Library
G.E. Co. Hanford Works - Project C-431-A production facility - Sec. A, subcontract G-363, revised design report
The 100-C project is to be located adjacent to the present 100-P Area. It is planned to build an addition to the present 181-B River Pump House using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and, therefore, protection against possible flood damage is assured.
Date:
March 29, 1951
Creator:
unknown
System:
The UNT Digital Library
Insulating webbing between thermal shield and graphite reflector
The purpose of this document is to present the bases and calculations which resulted in the conclusion given in the letter of October 17. Also, the original calculations were made on the basis that the webbing face thickness is equal to 1/2 inch, which is no longer the case. The new thickness is 3/4 inch. This alters the condition of heat generation. Consideration is given to the heat generation in the legs.
Date:
October 24, 1951
Creator:
unknown
System:
The UNT Digital Library
Interim report No.1, PT-105-403-P, installation and initial operation
The effect of temperature on the properties of graphite is being determined by exposing samples to pile neutrons at controlled temperatures in the range 75 C to 225 C. The first series of samples were charged into the newly installed dry, water-cooled test channel at B pile on January 23, 1951. This report presents details of the charging operation and observations noted during the initial operation of the test.
Date:
February 7, 1951
Creator:
Haussler, W. M. & Purcell, R. H.
System:
The UNT Digital Library
Proposed combination of neutralized concentration building wastes with neutralized 5-6 and second cycle wastes
None
Date:
August 31, 1951
Creator:
Gile, H. S.
System:
The UNT Digital Library
Report on decreasing available acceleration of 190-B process pump turbines in order to reduce emergency steam demand
As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amount in order to decrease the emergency steam demands and keep the combined steam demands of 100-B and 100-C Areas within the capacity of 184-B Boiler House, as outlined in Document HDC-2106, revised June 4, 1951. This report recommends that the desired results be obtained by simply reducing the speed setting of the turbine speed governors. No new equipment is needed. The setting of the emergency over speed trips would be left unchanged.
Date:
December 28, 1951
Creator:
unknown
System:
The UNT Digital Library
Calculation of activity induced in diatomaceous earth
None
Date:
January 9, 1951
Creator:
Lewis, M.
System:
The UNT Digital Library
Heating in the Graphite Due to a Cadmium Control Rod
From introduction: "This paper employs a multigroup method similar to that of J. S. Story, AERE-TR-177 to calculate, for cylindrical geometry, that heat energy source density in graphite due to absorption and Compton scattering of those gammas produced by neutron capture in a water filled cadmium control rod."
Date:
September 29, 1951
Creator:
Newkirk, W. H.
System:
The UNT Digital Library
Capacity survey -- Separations Division
Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentration step has been modified to permit the greater capacity. At 600 MWD/T (522 g/t) then, the 112 tons uranium per month capacity limits the plutonium output of the plant to 58.5 Kg per month at 80% operating efficiency. The remaining 38 Kg plutonium per month may be processed in the B and T BiPO{sub 4} plants at an operating efficiency of 89.5%; if this operating efficiency cannot be realized, the postulated production rate may be met by either an increased Redox efficiency or by accepting an increased plutonium waste loss of 1% on some portion of the BiPO{sub 4} production.
Date:
June 28, 1951
Creator:
Frame, J. M. & Tomlinson, R. E.
System:
The UNT Digital Library
Removal of ruptured slug from tube No. 2562-H
It is the purpose of this document to record the significant steps in the removal of a ruptured slug from tube {number_sign}2562-H.
Date:
February 12, 1951
Creator:
Haaga, J. A.
System:
The UNT Digital Library