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- 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.
- ABWR: PL-2 Design Report
- From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
- Adiabatic Injection
- From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.
- 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.
- 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.
- 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.
- Argonne National Laboratory Idaho Division Summary Report: July-September, 1960
- Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961
- Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
- Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961
- Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
- Carnotite resources of Outlaw Mesa, Mesa County, Colorado
- A report regarding carnotite resources of Outlaw Mesa, Mesa County, Colorado.
- Ceramic Investigations of UO₂
- This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
- Chemical Processing Instrumentation and Control Research Program
- Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
- Dibutyl Carbitol Solvent Extraction of Polonium-210 from Nitric Acid Solutions of Irradiated Bismuth
- Abstract: "A continuous countercurrent solvent extraction process utilizing dibutyl carbitol as the extractant has been developed for separating 210Po from large amounts of associated bismuth. Both laboratory and pilot plant data demonstrate the process is a suitable headend step in recovery of kilogram quantities of 210Po. Typically, the extraction process recovers over 98% of the 210Po, essentially free from bismuth (Bi DF>1500), in a dilute HNO3 solution suitable as a starting material for final concentration and purification steps."
- The Ductility of Brazed Stainless Steel Joints
- Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
- Effect of Plasma Oscillations on the Table-Top Model
- The following report describe the effect of plasma oscillations using a table-top model and the probable magnitude of the quantities needed to reach complete ionization.
- Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels
- Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)
- The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod
- Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."
- Electroplated Metals on Uranium for Aluminum Cladding
- Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
- The Elimination of Microwave Reflections
- Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
- Energetic Neutral Injection into Thermonuclear Machines
- Abstract: "A scheme is discussed in which D+ ions would be accelerated to about 100 kev in a conventional accelerator, then be sent through a gas target frmo which about half the ions would emerge neutral with very little scattering or energy loss; the neutral beam would then cross into a magnetic field and part of the atoms would be ionized and trapped by colliding with the already trapped ions. The smallest mirror machine with a central field of 30-40 kilogauss, 2;1 mirror ratio and β = 01 to 0.5 that would trap most of the neutral beam in the steady state, would be about a meter in diameter and require the order of hundreds of amperes of D+ ions into the neutralizer. The smallest stellerator with a field of 30 kilogauss and β = 0.1 that would trap most of the neutral beam would be about a meter long and require about 10 amperes of D+ ions. A preliminary mirror machine experiment that might be done using the 1/2-ampere, 100-kev D+ beam from the UCRL spare MTA injector is discussed. A method of starting these machine is discussed."
- Energy Transfer Between Modified Maxwell Distributions
- Abstract: "A particularly conventional modified form of Maxwell distribution is chosen. The modified expressions for (a) the energy transfer from the ions to the electrons in a plasma and (b) the brehmestrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions."
- Evaluation and Consolidation of Electrolytic Thorium
- Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
- Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors
- This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
- An "Exact" Analysis of a Cylindrical Plasma in a Magnetic Field
- Abstract: "The analysis of an immobilized plasma is here extended to the case where the geometry is cylindrical rather than Cartesian. (This report, UCRL-4439 (Rev, 4 constitutes Part II of the report series (UCRL-4466, Parts I, III, and IV) dealing with this general problem.)"
- An Exact Analysis of Limited Plane Plasma in a Magnetic Field
- Introduction: "Prior analyses of a plasma in a magnetic field have been limited, as far as the writer is aware, to cases in which the relative change in field over the orbital distance and the relative change in ion concentration are both small, or in which the relations have been viewed in a purely hydrodynamical way. The first approach excludes cases which can be of considerable interests, for it fails near a plasma edge. The second loses all sight of the structure imposed by the orbital motions."
- Extrusion Cladding of Fuel Element
- From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."
- The Fabrication of Subassemblies for the Supercritical-Water Reactor
- In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UO₂ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
- Final Safeguards Summary Report for the Piqua Nuclear Power Facility
- Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
- Final Summary Report of the Gas-Cooled Reactor Experiment-1
- Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
- 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.
- Fort McClellan Radiological Instruction Area (ARMS-II)
- Report documenting the survey of the U. S. Army Chemical Corps Schoo, Radiological Instruction Area, Fort Mclellan, Alabama. This survey measures radiation an d gamma-ray flux in an approximately one square mile area.
- Further Studies on Large-Batch Melting of Uranium
- The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.
- Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions
- Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 and 0.033 mm."
- Ground Roughness Effects on the Energy and Angular Distribution of Gamma Radiation From Fallout
- Report examining "[t]he effect of ground roughness, or surface irregularities, on the radiation field above ground which had been contaminated with fallout from the explosion in the atmosphere of a nuclear device (Smallboy Event)" (p. v).
- The HASL Bone Program 1961-1964
- Report documenting the measuring of strontium-90 levels contained in the bones of children and adults of various age brackets across the United States.
- High-Energy Peripheral Injection into Mirror Machines
- The following report proposes various methods in injecting and heating in mirror machines, using high-energy ion beams.
- 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.
- ICPP Waste Calcining Facility : Safety Analysis Report
- Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
- Initial Measurements on the Angular Distribution of Deuterium Plasma Produced by a Pulsed Spark Source
- Abstract: "The deuterium plasma which is ejected by a 6000-ampere pulsed current through a rail-type spark source has a yield in the forward direction which is a factor of 5 to 10 greater than that in the perpendicular direction. This effect is believed to be due to the magnetic propulsion of the plasma."
- 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.
- 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.
- 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
- Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev
- Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
- Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958
- Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.
- Location of Orbital Axis in Table-Top Stellarator
- This report discusses what effects the shift of an orbital axis relative to the center of the table-top stellarator tube as well as the magnitude of these effects.
- Magnetic Acceleration of a Plasma by a Rail Source
- Abstract: "Two parallel wires close together with an arc between them form a hairpin-type of current configuration which should magnetically propel the plasma of the arc. By the time-of-flight measurements with probes it has been demonstrated that directed translational energies of 290 ev can be imparted to deuterons in a plasma produced by a high-current pulsed arc at the tips of two titanium wires loaded with deuterium. It is believed that three deuterons are actually magnetically propelled."
- 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.
- Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes
- Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."
- Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
- Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
- Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
- Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."