Resource Type
Serial/Series Title
Atomic Energy Commission Reports
311
NACA Research Memorandums
115
AEC research and development report
89
Hanford Works Reports
71
HW (Series)
58
NACA Technical Reports
46
North American Aviation Reports
45
Health and Safety Laboratory Reports
42
General Electric Company Atomic Power Reports
41
TID
41
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731 Matching Results
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Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy
Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date:
February 1, 1965
Creator:
Willard, R. M. & Schmitt, A. R.
Object Type:
Report
System:
The UNT Digital Library
Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide
Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
Date:
December 1, 1964
Creator:
Guon, J.; Bodine, J. E. & Sullivan, R. J.
Object Type:
Report
System:
The UNT Digital Library
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date:
February 1, 1965
Creator:
Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
Object Type:
Report
System:
The UNT Digital Library
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
Date:
March 1, 1965
Creator:
Blevitt, R.; Paine, G. & Sudar, S.
Object Type:
Report
System:
The UNT Digital Library
Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits
Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date:
February 1, 1963
Creator:
Holland, J. W.
Object Type:
Report
System:
The UNT Digital Library
KEWB Program Quarterly Progress Report: July-September 1956
From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date:
March 1, 1957
Creator:
North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
Object Type:
Report
System:
The UNT Digital Library
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
Abstract: The following report covers the final design of the modular steam generators.
Date:
February 1, 1965
Creator:
Casey, D. F.; Hammer, J. J.; Logan, D. & Williams, M. C.
Object Type:
Report
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963
From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
Date:
March 1, 1964
Creator:
Darley, D. K.
Object Type:
Report
System:
The UNT Digital Library
Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment
Introduction: A series of critical and subcritical experiments have been carried out as part of the Advanced Sodium Graphite Reactor (ASGR) Critical Experiments program to provide physics information which would be directly applicable to the AGSR concept.
Date:
December 1, 1964
Creator:
Hillig, O. R. & Latham, D. W.
Object Type:
Report
System:
The UNT Digital Library
Boiling Depressurization Transients
Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date:
August 1, 1964
Creator:
Halfen, F. J. & Berganzoli, F.
Object Type:
Report
System:
The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date:
March 1, 1962
Creator:
Cappel, H. H.
Object Type:
Report
System:
The UNT Digital Library
Thermal Stress Testing of Beryllium Oxide Moderator Shapes
Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date:
August 1, 1962
Creator:
Sujata, H. L.; King, M. & Waters, F. J.
Object Type:
Report
System:
The UNT Digital Library
Uranium Carbide Transient Heating Experiments - Phase 1
Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date:
August 1, 1964
Creator:
Stachura, S. J.; Silberberg, M. & Cordy, R. N.
Object Type:
Report
System:
The UNT Digital Library
The Chemical Effects of 1 Mev Electrons on BrF3 at 25 degrees C
"An investigation of the chemical effects of 1-Mev electrons on BrF3 at 25 degrees C has been carried out. Pressure measurements taken during the irradiation suggest the presence of Br2 and BrF5 as decomposition products and a fractional distillation of the irradiated liquid confirmed their presence. The extent of decomposition was determined both by fraction distillation and spectrophotometric methods. The radiation effect seemed to reach saturation when approximately 10 per cent of the BrF3 was destroyed. The exposure necessary for the decomposition products to reach a concentration of half the saturated value was calculated to be 2.7 microampere hours/cc BrF3 while the "G" value was found to be 1.5. A qualitative comparison of irradiation dosages from the Statiltron with that expected from spent fuels revealed that little decomposition of BrF3 reagent is to be expected from 1-say cooled Hanford fuel (in pile for 100 days) while in the case of 1-day cooled MTR type fuel (in pile for 12 days) a saturated effect might be realized in 1-3 hours. Since at most only 10 per cent of the BrF3 is destroyed it is concluded that BrF3, from a radiation resistance standpoint, is a suitable standpoint, is a suitable reagent for …
Date:
October 1, 1954
Creator:
Yosim, S. J.
Object Type:
Report
System:
The UNT Digital Library
Sodium Graphite Reactor, Quarterly Progress Report, March-June 1954
"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …
Date:
September 1, 1954
Creator:
Siegel, Sidney & Inman, Guy M.
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945
Technical report with short reports covering (1) Effect of radiation on water and aqueous systems; (2) Effect of neutrons on graphite; (3) Effect of radiation on solid compounds; and (4) Scattering, stopping-power, ion-pair production, etc.
Date:
February 1, 1945
Creator:
Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
Object Type:
Report
System:
The UNT Digital Library
Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2]
Abstract. thorium can be precipitated as a salt of p-dimethylaminoazophenylarsonic acid at a pH of about 1.5. the precipitate, collected on a sintered glass filter is washed with dilute ammonium hydroxide to dissolve the dye. the amount of thorium is determined by measuring the concentration of the dye spectrophotometrically at a wavelength of 450 millimicrons. Zirconium, which interferes, can be separated and determined using the same reagent in strong hydrochloric. the behavior of thorium metal upon treatment with various acids and upon fusion withKHSO4 is described. three satisfactory procedures are given for dissolving the metal with sulfuric acid, phosphoric acid, and by a potassium hydrogen sulfate fusion. The laboratory was presented with the problem of analyzing for a large number of elements in O2 metal. the results of a systematic study of methods for effecting solution of the metal are offered here since they may be of some interest and use to other laboratories. The four methods which effected complete solution of the metal are (1) Sulfuric acid method; (2) Fusion method; (3) Phosphoric acid method; and (4) Nitric acid-hydrofluoric acid method.
Date:
January 1, 1945
Creator:
Byerly, W.; Niedrach, L.; Davin, W.; Dyas, H. & Bane, R. W.
Object Type:
Report
System:
The UNT Digital Library
Thermal Conductivity of Silicon and Iron From 300 to 1400°K
From Abstract : "The thermal diffusivities of pure silicon and of Armco iron have been measures from 300 to 1400°K. The specific heats of the same materials have been measured over the same temperature range."
Date:
January 1, 1963
Creator:
Klein, A. H.; Shanks, H. R. & Danielson, G. C.
Object Type:
Report
System:
The UNT Digital Library
Hydrogeochemical and Stream-Sediment Survey : Preliminary Report on the Smoke Creek Desert Basin Pilot Study (Nevada)
This report follows the hydrogeochemical and stream-sediment study in the Smoke Creek Desert Basin in Nevada that was conducted by the Lawrence Livermore Laboratory. This report contains only the analytical data and sample locations.
Date:
August 1, 1976
Creator:
Lawrence Livermore Laboratory
Object Type:
Report
System:
The UNT Digital Library
Hydrogeochemical and Stream-Sediment Survey (NURE): Preliminary Report on the Roach Lake Basin Pilot Study (Nevada)
This report follows a hydrogeochemical and stream-sediment study taken in the Roach Lake Basin by the Lawrence Livermore Laboratory. This report contains only the analytical data and sample locations.
Date:
August 1, 1976
Creator:
Lawrence Livermore Laboratory
Object Type:
Report
System:
The UNT Digital Library
The Synthetic Liquid Fuel Potential of Nebraska
Report documenting the suitability of Nebraska for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest
Date:
November 1, 1950
Creator:
Ford, Bacon, and Davis
Object Type:
Report
System:
The UNT Digital Library
A Study of Thorium Peroxide Sulfate
Abstract. Thorium peroxide was precipitated from thorium nitrate solutions containing varying amounts of sulfate ion and of hydrogen ion. The washed solids were analyzed both wet and dry. Analyses were made for thorium, peroxide oxygen, sulfate, nitrate, and water contents. X-ray powder photographs of the dried samples by W.H. Zachariasen showed the presence of only two phases. When precipitated from high sulfuric acid, the solid phase was isomorphous with Th(OO)SO4.3H20. More weakly acid solutions whose sulfate content was varied over wide limits [SO4--/Th(IV) (in solution before precipitation) = 0.005 to 67.0] yielded a solid, isomorphous with thorium peroxide nitrate and containing 3.0 to 3.8 peroxide oxygen atoms for each thorium atom. The sulfate content of this latter phase varied continuously between the limits SO4--/Th(IV) = 0.34 to 0.01 with nitrate ion present when the sulfate content was very low. This continuous variation in composition is in agreement with the previously proposed structure of this phase.
Date:
October 1, 1945
Creator:
Hamaker, John W.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of Beryllium: a Bibliography
This bibliography contains 147 references on the fabrication of beryllium. References are also given on the brazing, casting, cladding, extrusion and welding of beryllium and some beryllium-rich alloys. The bibliography is limited to the period 1950 - 1959. references are arranged alphabetically by title, with author and subject indexes provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program - Classified and Unclassified Versions, Engineering Index, Nuclear Science Abstracts, TISE, List of Bibliographies in the Atomic Energy Program.
Date:
April 1, 1960
Creator:
Cernak, Elizabeth A.
Object Type:
Report
System:
The UNT Digital Library
Chain Reaction of Pure Fissionable Materials in Solution
The critical mass of 94-239 and the corresponding critical dimensions of homogeneous mixtures of 94-239 with various moderating media been calculated as a function of the concentration of 94. A simple transformation makes the figures applicated to92-235. the results are in essential agreement with the preliminary estimated made independently by Oppenheimer and Serber. The problem of the stability of a chain reaction in solution and questions of protection are discussed.
Date:
January 1, 1943
Creator:
Christy, Robert F., 1916-2012 & Wheeler, John Archibald, 1911-2008
Object Type:
Report
System:
The UNT Digital Library