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Leaching and Precipitation Tests on Grants Ores

Description: Leaching tests were run on two samples from the Grants area in New Mexico. Uranium extractions of 94 per cent were obtained by leaching Sample 6-1 with solutions containing 240 lbs. of Na2CO3 and 60 lbs. of NaHCO3 per ton and by leaching Sample 6-2 with 270 lbs. of Na2CO3 and 180 lbs. of NaHCO3 per ton. Cyclic tests were completed using caustic precipitation of the leach liquor.
Date: September 10, 1951
Creator: Abrams, Charles S. & George, D'Arcy R.
Item Type: Refine your search to only Report
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Sweeping of Fission Gases from Solutions of U and Plutonium

Description: Technical report describing two experiments performed to compare the amounts of fission gases swept out of UNH solution with those amounts swept out of PU solution under idential condiditons. The charge wire technique was used. The essential date and the results are given in tables in the report.
Date: September 4, 1945
Creator: Adams, R. M. & Finkelstein, H.
Item Type: Refine your search to only Report
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design

Description: This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be encl… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis

Description: Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to mainta… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications

Description: Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
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Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance

Description: This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
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Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator

Description: The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifica… more
Date: September 14, 1962
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
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Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Description: Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
Item Type: Refine your search to only Report
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Limits of Inflammability and Ignition Temperatures of Hexone in Air and in Other Gaseous Atmospheres

Description: The following report summarizes the data taken from a series of measurements on the combustion and ignition properties of hexone. The experiments were taken at the Bureau of Mines Central Experiment Station by their personnel, and the samples were given to them by KAPL and Hanford.
Date: September 9, 1949
Creator: Alter, H. Ward
Item Type: Refine your search to only Report
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Occurrence of Technetium in Nature : Final Report for the Period November 1, 1954 to August 31, 1955

Description: Twelve neutron activation analyses for naturally occurring technetium-98 were performed. Positive results were obtained in ten cases. Precautions were taken to avoid interference by molybdenum and technetium-99. the cross section for the reaction [formula] as found to be equal to 4 +- 2 mb for the neutron spectrum of the vertical thimbles of the Argonne CP-5 reactor. The chemical state of molybdenum (VI) in basic solution was studied by an anion-exchange technique. Evidence was obtained for the… more
Date: September 1, 1955
Creator: Anders, Edward, 1926-
Item Type: Refine your search to only Report
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Fuel Failure Examinations and Analyses in the High Power Density Program

Description: Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigat… more
Date: September 16, 1963
Creator: Arlt, W. H. & Vandenberg, S. R.
Item Type: Refine your search to only Report
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Control of the Dissolved Gases in the Moderator of the HWCTR

Description: The Heavy Water Components Test Reactor (HWCTR) is used to test prototype fuel elements for power reactors that are moderated with heavy water and fueled with natural or slightly enriched uranium. During the initial critical experiments in the HWCTR, it was observed that there were unexpected variations in nuclear reactivity. Investigations revealed that this effect was due to bubble of helium gas appearing and disappearing in the moderator. An examination of the expected operating conditions… more
Date: September 20, 1963
Creator: Arnett, L. M.
Item Type: Refine your search to only Report
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Uranium Concentration Meter

Description: From abstract; "Two basic instruments were developed for determining the concentration of uranium in solutions. Both instruments detect the gamma activity present in a sample solution, and interpret this analysis into direct presentation as parts per million."
Date: September 24, 1956
Creator: Arnett, Orville
Item Type: Refine your search to only Report
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: September, 1957

Description: A monthly report summarizing work performed by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this month's report comparison of second two-dimensional calculation with the equivalent one-dimensional calculations was performed, reference design core modifications were completed, along with continued work on the design of the core and containment vessel for a LMRFE.
Date: September 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
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Airborne Reconnaissance in the Valley of Fire-Muddy Mountains Region, Nevada

Description: Abstract: The Valley of Fire-Muddy Mountains region, located 20 to 30 miles northeast of Las Vegas, Nevada, was given approximately 25-percent airborne radioactive coverage during the fall of 1954. Rocks in the area range from Cambrian to Miocene in age. Uranium was known to occur at two sedimentary horizons at the time the airborne program began. One new uranium-bearing sedimentary horizon was discovered by the airborne reconnaissance. Of 15 anomolies detected, only 11 were posted as the remai… more
Date: September 1955
Creator: Barrett, Donald C. & Mallory, Neil S.
Item Type: Refine your search to only Report
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An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor

Description: 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.
Item Type: Refine your search to only Report
open access

Half-Life of Polonium

Description: Abstract: "The half-life of polonium has been measured by a calorimetric method using samples several thousand times larger than have been previously available. The value is found to be 138.3 +/- 0.1% days."
Date: September 9, 1946
Creator: Beamer, William H. & Easton, William E.
Item Type: Refine your search to only Report
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