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- Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report
- This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
- An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
- From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
- An Air-Borne Densitometer for Smoke Concentration Measurements
- A simple, light-weight, split beam optical smoke densitometer is described.
- The Alco Products Inc. Criticality Facility : Description and Operation
- The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.
- An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
- Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
- Aluminum Titanate as a Ceramic Material
- A report on using aluminum titanate as a ceramic materiel.
- Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2
- Introduction: This report is principally concerned with analysis of measurements taken on the APPR-1 core during the course of the extended Zero Power Experiments (ZPE-2). The bulk of these measurements are reported in APAE No. 21. There are some additional measurements reported in APAE Memo 115. In addition to the analysis of the ZPE-2 data some re-evaluation has been made of a few of the results obtained from the first set of Zero Power Experiments (ZPE-1). The ZPE-1 measurements are reported in APAE No. 8. During the course of analysis work it became apparent that a considerable amount of basic experimental data had been taken on the APPR-1 core. It seemed worthwhile to organize this report in such a fashion that other investigators could make maximum use of this data. It provides excellent opportunity for individuals and groups interested in basic reactor reactor analysis problems to check calculational techniques. An attempt has been made to include all of the fundamental information concerning the material content and geometry of the APPR-1. This material is in included in the Appendices. In addition, cross-section files and group constants have been listed rather extensively in order that other investigators could compare results presented in this report with those obtained by other techniques. Listing are generally given to six places although not all of these places are significant. This was done so as to avoid round off error.
- APPR-1: Design, Construction and Operation
- "This document includes papers covering technical problems involved in the design, construction and operation of the APPR-1" (p. 4).
- APPR-1 Research and Development Program. Design Analysis for Flow and Temperature Measurement Program, Task No. 5
- From objectives: "To establish, by literature search, analysis and design, the engineering and fabrication requirements for modifying reactor components and developing and installing the necessary instrumentation to carry out a fuel temperature and flow measurement experimental program."
- Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual
- Report containing basic operating instructions for the operation of the Army Package Power Reactor. This includes descriptions of the the plant's systems, operations, and safety procedures.
- Army Package Power Reactor: Description and Supplement
- Various hazards associated with the APPR-1.
- An Automatic Analyzing Monitor for Reactor Effluent Cooling Water
- From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
- Boiling Homogeneous Reactor for Power and U233 Production: Reactor Design and Feasibility Problem
- Summary report of the study, research, problems and solutions developed in the final ten-weeks period of the school term for a group of men representing various scientific and engineering fields.
- Chemical processing methods and economics for various liquid metal fuel reactors
- From abstract: "The economic factors of chemical processing of the fuel and blanket from liquid bismuth fuel reactors are described and evaluated."
- A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals
- Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
- Conversion of UNH to UO3 : Terminal Report
- Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.
- The Corrosion of Refractory Materials in Sodium
- Analytical methods for the presence of the refractory substances in sodium are described.
- Cost Estimate for the Food Irradiation Reactor
- Study conducted for the U. S. Army Reactors Branch of reactors for the irradiation of food.
- The Crystal Structure of Uranium Tetrafluoride
- Fourier refinement analysis of the uranium parameters in uranium tetrafluoride.
- Decontamination Program Task II. Volume 1, Contamination and Decontamination in Nuclear Power Reactors
- Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caustic permanganate treatment followed by and acid rinse.
- Decontamination Program Task II. Volume II, Evaluation of Chemical Agents for Nuclear Reactor Decontamination
- Abstract: The caustic permanganate-rinse decontamination treatment was investigated. Loop and metallurgical studies were performed to determine optimum operating conditions as well as the metallurgical effects of the treatment. A treatment with 10 percent sodium hydroxide and 5 percent potassium permanganate solution followed by a rinse with a 5 percent ammonium citrate, 2 percent citric acid and 1/2 percent Versene solution was chosen for the decontamination of a stainless steel steam generator. Decontamination factors of greater than 50 were obtained in loop tests using the above treatment. Corrosion and metallurgical results indicated a total penetration of less than 0.01 mil on annealed Type 304 stainless steel with no evidence of any deleterious effects.
- Decontamination Program Task II. Volume III, Recommended Procedure for Decontamination of a Stainless Steel Steam Generator
- Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.
- Degassing Sparger Plate Screening Tests
- Results of tests to remove fission gases, xenon and krypton, formed during the operation of a nuclear reactor.
- Description and Some Safeguard Aspects of Proposed Developmental Fast Neutron Breeder Reactor
- 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.
- 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.
- Description of Purex Plant Process
- Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
- Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location
- Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
- Design Analysis of a Prepackaged Nuclear Power Plant: Volume 1, Primary and Secondary System Design
- Design analysis of a prepackaged nuclear power plant.
- Design Analysis of a Prepackaged Nuclear Power Plant: Volume 2, Reactor Design Analysis
- Design analysis of a prepackaged nuclear power plant.
- Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks
- Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
- Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
- Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
- Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor
- Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.
- Effect of Process Variables on Graphite Purity
- Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.
- The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete
- Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
- The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores
- Effect of x irradiation in oxygen and in hydrogen on chromosome aberration frequency in tradescantia microspores.
- Electronic Analog Computer Study of a Nuclear Reactor Steam Pressurizer
- Study consists of setting up the computer on the situation representing test vessel and setting up the full size pressurizer vessel on the analog computer.
- Engineering Study on Underground Construction of Nuclear Power Reactors
- Engineering study on underground construction of nuclear power reactors.
- Engineering Test Reactor : Engineering Design and Safeguards Report
- From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
- Extraction of Thorium Nitrate from Nitric Acid by TBP - "Ultrasene"
- Equilibrium data are presented for the distribution of thorium nitrate and nitric acid between aqueous solutions and tri-n-butyl phosphate diluted with kerosene.
- Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes
- Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
- Facilities for Investigation of Power Pile Materials in the High Flux Pile
- Estimation of internal facilities required in the high-flux pile for research on materials for power-producing piles and components.
- Facilities for Irradiation Within the MTR Reactor Tank
- Information on experimental facilities and reactors.
- Factors Affecting Fluidization of Uranium Trioxide Powders
- Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
- Fall-Out in Southeastern United States During January and February 1951 from the Nevada Atomic Tests
- Air filter and rainwater collections of atmospheric fall-out were made at Atlanta, Georgia; Urbana, Illinois; Topeka, Kansas; Fort Worth, Texas; and Nashville, Tennessee. Collections reflect the effects of the radioactive cloud from the Nevada tests.
- Fast Neutron Data
- A report concerning fast neutrons including theory and compiled data.
- Feasibility Study of Pressure Vessels for Nuclear Power Generating Reactors
- Design fabrication and feasibility studies of four reactor pressure vessels for U. S. Atomic Energy Commission.
- Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices
- From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."
- Final Design Report KAPL-120 High Pressure Recirculating Water Loop
- Basic information on the design of the Knolls Atomic Power Laboratory (KAPL) -120 loop.
- Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity
- A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
- Floating-Decimal Matrix Inversion
- Use of Crout Method in floating-decimal notation in IBM Model I Card-Programmed Calculator.