UNT Libraries Government Documents Department - 766 Matching Results
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- Process Engineering Report on Production of Thorium at Iowa State College
- Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.
- FMPC Solvent Treatment Area - Process Design
- This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
- Annual Technical Progress Report, AEC Unclassified Programs: 1965
- Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1964-65 fiscal year.
- Quarterly Technical Progress Report, AEC Unclassified Programs: July-September 1965
- Quarterly report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the first quarter of the 1966 fiscal year.
- Annual Technical Progress Report, AEC Unclassified Programs: 1966
- Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.
- Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 8: 1966
- The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
- Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 9: 1966
- The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
- Carnotite resources of Outlaw Mesa, Mesa County, Colorado
- A report regarding carnotite resources of Outlaw Mesa, Mesa County, Colorado.
- Results of exploration at Lost Creek schroeckingerite deposit, Sweetwater County, Wyoming, July 1951-February 1952: an interim report
- "his interim report presents the grade and tonnage data collected during exploration at the Lost Creek schroeckingerite deposit, Sweetwater County, Wyoming, Between July 1951 and February 1952. Discussions of he geologic results of exploration (lithology, mineralogy, structure, origin, etc.) are not included in this report and consequently the detailed lithology and structure have been omitted from the illustrations (figs. 1-7)"
- Second-cycle airox reprocessing and pellet refabricating of highly irradiated uranium dioxide
- "This report describes second-cycle postirradiation examination and AIROX reprocessing-refabricating of uranium dioxide irradiated to an additional 10,000 Mwd/MTU burnup."
- Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review
- A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review
- Safety Evaluation of PNPF Modifications
- "The purpose of this report is to examine the safety aspects of PNPF restart on continued operation, after completion of the core cleanup and system modifications."
- UNICORN: a program to calculate point cross sections from resonance parameters
- A report regarding Unicorn - a program used to calculate point cross-sections from resonance parameters.
- Irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
- A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
- Quarterly Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968
- Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
- High heat flux heater development status report
- The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.
- Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968
- Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
- Interim report on exploration of the Jo Dandy area, Montrose County, Colorado
- Interim report regarding an exploration of the Jo Dandy area, Montrose County, Colorado. Concerns work done on the behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.
- Preliminary report on exploration in the Atkinson Mesa area, Montrose County, Colorado
- A preliminary report regarding exploration in the Atkinson Mesa Area, Montrose County, Colorado
- Preliminary report on diamond-drill exploration on Outlaw Mesa, Mesa County, Colorado
- Preliminary report regarding diamond-drill exploration on Outlaw Mesa, Mesa County, Colorado. Done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission
- Doppler and related measurements in a soft fast-reactor spectrum
- This report deals with a group of both theoretical and experimental investigations which have been carried out, utilizing Core 15, one in a series of critical assemblies that have been constructed at Atomics International's Epithermal Critical Experiments Laboratory (ECEL).
- Ionium Recovery Plant Design Report: Topical Report
- This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
- Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3
- This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
- The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation
- An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.
- The Anodizing of Zirconium
- Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.
- Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV
- Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nuclear evaluation, thermal and hydraulic analysis, description of tests to be performed, and discussion of containment integrity and maximum accident considerations.
- Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups
- Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel mockups are presented. The uncertainties associated with the measurements are also given. In addition to graphical and tabular presentations of the test results, discussions are provided on the experimental techniques and theory. A review of the analytical models is provided in addition to the calculational results. A special analytical study of the the PM-2A Core I power distribution and absolute power level determination is given. A comparison of the experimental and analytical results is made and conclusions and recommendations presented.
- Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants
- Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and the results of non-destructive and destructive metallographic analyses.
- PM-2A Core II Zero Power Experiment
- Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of experimental data. Physical characteristics determined include distribution of fuel and B-10 in the fuel plates, minimum critical mass, control rod bank calibration, and integral rod worth. The report concludes with an analysis of the experimental data including estimated uniform and non-uniform burnup rates.
- The Shielding of Mobile Reactors - [Part] 2
- From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, are finally compared with the experimental data."
- Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending December 10, 1951
- This quarterly progress report details the ongoing research and experiments at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. The first part of this report discusses reactor theory and design. The second part of this report is not included. The third part of this report discusses materials research. The fourth part of this report includes appendixes
- Sigma Plug Welding of Spun-Over Fuel Cans
- Summary: Purpose of the investigation is to improve the peripheral welding of the brazed joint at the top of aluminum-sheathed fuel slugs by forming the can over the top of the cap and welding the resulting center opening. This investigation looked at the applicability of the inert-gas-shielded, consumable electrode process, using commercially available equipment, for producing a weld closure in spun-over fuel cans. Using commercially available sigma welding equipment, no practical combination of welding conditions was found which resulted in satisfactory leak-tight closures in spun-over canned fuel slugs. It is recommended that plug welding of spun-over closures by the sigma welding process be dismissed from consideration for start-up at the Savannah River Plant.
- A Simple Leak Detector for Tritium
- From abstract: "An ionization chamber of the integrating type was built that could detect a tritium leak rate of 10[^-13] cc per second within a few minutes, after a gas-collecting period of 16 hours. Electronic circuitry was avoided by using a quartz fiber voltmeter to indicate the rate of discharge of the chamber."
- Summary Report on Thorium Metal Quality for Production Reactor Use
- From abstract: "Background material leading to the development of the metal quality of reactor-grade thorium is given. The metal should be sound and of uniform hardness, free of internal cracks and inclusions, and corrosion resistant. It should contain only small amounts of natural uranium, thorium oxide, and elements that act as reactor poisons. Because of their effect upon metal quality, various methods for the production of thorium are discussed. Use of consumable electrode arc melting as the final step has contributed much to the production of thorium of excellent quality for reactor use."
- Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963
- Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
- Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963
- Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows no size effect in the range of pipe sizes from 3/4 inch to 1-1/4 inch. The values lie below the Martinelli curve at the lower qualities (x<0.6), but at high qualities tend to be above the Martinelli curve. The single-phase loss coefficient for the three contraction-expansion inserts show very little Reynolds number effect in the range of channel Reynolds numbers from 3 x 10(4) to 5 x 10(5). The two-phase data for insert number 1 has not yet been reduced. The two-phase loss for insert numbers 2 and 3 lies generally below the loss prediction based on a homogeneous flow model. The two-phase loss for insert number 2 shows excellent agreement with the corresponding loss for the S-1 insert in the 1/2- by 1-3/4-inch rectangular channel reported earlier. The two-phase loss for insert number 3 agrees fairly well with the loss for the S-5 insert.
- Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)
- The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
- Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)
- The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
- Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fourth Quarterly Progress Report, January 1-March 31, 1963
- Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. Boric acid experiments and Humboldt Bay experiments are reported.
- Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 2
- The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.
- Summary Report of Analysis of Physics Measurements Performed on SM-1 Core I
- Abstract: This technical report contains a comprehensive analysis of the nuclear characteristics of the SM-1 Core I. Comparison of analytical and experimental results for neutron ages and core reactivities of a variety of cases investigated shows that the MUFT III with P-1 slowing down approximation gives the best results. At startup the core reactivity and rod bank worth under various operating conditions are investigated and compared to experiment. Core lifetime was calculated to be 16.8 MWYR compared to 16.4 MWYR experimental. The temperature coefficient has been calculated and compared to experiment as function of burnup. In Appendix A, flux distribution, temperature coefficient, effective delayed neutron fraction and core life are analyzed by Dr. R. L. Murray by one and two group modified theory series expansion calculations.
- Summary Report of Physics Measurements on SM-1 Core I
- Abstract: This technical report summarizes all core physics experiments performed on SM-1 Core I and SM-2 Rearranged and Spiked Core I throughout core life. These measurements were obtained on site during the 16.4 MWYR lifetime of SM-1 Core I and 1.6 MWYR lifetime of SM-1 Rearranged and Spiked Core I. SM-1 Core I was the first stainless steel - UO2 dispersion core to burn out in the Army Nuclear Power Program. Experimental techniques are described and a complete history of fuel movements in the core presented. Measurements include control rod bank positions during all core conditions, temperature and pressure coefficients, control rod calibrations, transient poison effects, source multiplication, and stuck rod positions. The effect of core rearrangement and spiking on core reactivity and core life is also reported. Applicable measurements from the SM-1 zero power experiments are included.
- Nuclear Reactor Project Progress Report, January 1948
- This report is a progress report detailing operations and ongoing projects at the Brookhaven National Laboratory. The report describes new developments with buildings and progress regarding ongoing experiments. The report includes photographs showing progress in the construction of the reactor and other images and figures that accompany the descriptions of projects.
- Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951
- This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses thorium research, the mechanical properties of metals including thorium, uranium, inconel, and z-nickel, the ANP program (including the following topics: the physical chemistry of liquid metals, and welding research), and the materials testing reactor program.
- 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.
- Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951
- The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.
- Materials Testing Reactor Project Handbook
- The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
- Reactor Shielding Design Manual
- The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
- A 37,500 KW Power Reactor with Competitive Possibilities
- The following report follows the study on economics of nuclear power generation using a light water reactor.
- Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965
- Introduction: "This progress report is the twenty-sixth in a series presenting research and development activities in the field of radioactive wastes. Experimental work charged to programs other than those of the Division of Reactor Development is included for general interest and completeness; such work is identified in the headings."