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The Neutron Sensitive PCP Ionization Chamber
Manual of operation for a neutron sensitive ionization chamber for reactor instrumentation.
Date:
September 4, 1951
Creator:
Abele, R. K. & Gundlach, J.
Object Type:
Report
System:
The UNT Digital Library
Leaching and Precipitation Tests on Grants Ores
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.
Object Type:
Report
System:
The UNT Digital Library
Sweeping of Fission Gases from Solutions of U and Plutonium
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.
Object Type:
Report
System:
The UNT Digital Library
Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)
Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
Date:
September 1964
Creator:
Aerojet-General Corporation
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design
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 enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a …
Date:
September 30, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis
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 maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions …
Date:
September 30, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications
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).
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance
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 Detector, and (d) Sodium Purity Control Recommendations.
Date:
September 30, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator
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 specifications for which they were designed. Welding techniques for type 316 stainless steel are described. The specifications and operating conditions of the units are given along with instrumentation drawings showing test equipment design and arrangement.
Date:
September 14, 1962
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies
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.
Object Type:
Report
System:
The UNT Digital Library
Limits of Inflammability and Ignition Temperatures of Hexone in Air and in Other Gaseous Atmospheres
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
Object Type:
Report
System:
The UNT Digital Library
Occurrence of Technetium in Nature : Final Report for the Period November 1, 1954 to August 31, 1955
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 existence of polymeric species at pH-values up to 14. Preliminary work on the stability of Domax-1 anion exchange resin in perchlorate media indicates rapid deterioration even at 0.2F ClO4-.
Date:
September 1, 1955
Creator:
Anders, Edward, 1926-
Object Type:
Report
System:
The UNT Digital Library
Reconnaissance for uranium deposits in the Kaiparowits Plateau region, Utah
A report discussing a geologic reconnaissance of a section of the Kaiparowits Plateau region of Utah was conducted to evaluate the uranium potential of the area.
Date:
September 20, 1956
Creator:
Annes, E. C.
Object Type:
Report
System:
The UNT Digital Library
Fuel Failure Examinations and Analyses in the High Power Density Program
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 investigation of lower cost fabrication processes and the irradiation testing of fuel elements fabricated by these processes. Both tasks include the investigation of the feasibility and use of thin-wall stainless steel cladding as a means of improving the neutron economy and fuel cycle costs of stainless steel clad fuel. Irradiation of the Task 1A fuel assemblies in the VBWR was initiated in September, 1960. Subsequently, Task 1B fuel assemblies were inserted in the VBWR as various fabrication processes and design concepts were investigated. Fuel cladding failures have occurred in fuel rods in both Task 1A and 1B. As of this date, cladding failures have occurred in twenty-two rods of approximately 700 fuel rods which have been irradiated. Twenty of the failures …
Date:
September 16, 1963
Creator:
Arlt, W. H. & Vandenberg, S. R.
Object Type:
Report
System:
The UNT Digital Library
Control of the Dissolved Gases in the Moderator of the HWCTR
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 of the HWCTR and the solubility of helium in D2O showed that it was possible during normal operation for the helium content of the moderator to exceed saturation and thus for helium to appear as bubbles in the moderator. The possibility of helium bubbles appearing in the moderator because of solubility characteristics was eliminated by modifications to the process system so as to maintain the gas content of the moderator appreciably below saturation.
Date:
September 20, 1963
Creator:
Arnett, L. M.
Object Type:
Report
System:
The UNT Digital Library
Uranium Concentration Meter
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
Object Type:
Report
System:
The UNT Digital Library
Description of Developmental Fast Neutron Breeder Power Reactor Plant
Report that generally describes sodium cooled fast reactors, the features and facilities of such a reactor proposed by Atomic Power Development Associates, and then its safety and siting considerations.
Date:
September 1, 1955
Creator:
Atomic Power Development Associates
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: September, 1957
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
Object Type:
Report
System:
The UNT Digital Library
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date:
September 1965
Creator:
Baker, James L. L.
Object Type:
Report
System:
The UNT Digital Library
Liquid Reactor Fuels: Bismuth-Uranium System
Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.
Date:
September 15, 1950
Creator:
Bareis, D. W.
Object Type:
Report
System:
The UNT Digital Library
Airborne Reconnaissance in the Valley of Fire-Muddy Mountains Region, Nevada
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 remainder were claimed at the time of the survey.
Date:
September 1955
Creator:
Barrett, Donald C. & Mallory, Neil S.
Object Type:
Report
System:
The UNT Digital Library
Cross Section for the Formation of Be⁷ from Oxygen Irradiated with High Energy Deuterons
Abstract: "The cross section for the formation of Be⁷ from oxygen irradiated with high energy deuterons has been determined. The values are 4.5 millibarns at 100 Mev, 5.6 millibarns at 150 Mev, and 5.5 millibarns at 190 Mev."
Date:
September 1953
Creator:
Batzel, Roger Elwood & Coleman, G. H.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Half-Life of Polonium
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.
Object Type:
Report
System:
The UNT Digital Library