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- 0-2 kv Flash Tube Supplies
- In order to perform the various experiments with a bubble chamber, a high intensity flash tube is used. This report briefly describes the power supplies designed and constructed to power these lamps.
- 6 kv Capacitor Charging Supply
- The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)
- An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation
- The present study was motivated by an attempt to understand low energy [formula] scattering within the framework of the bootstrap principle and the un-Reggeized version of the strip approximation. This work attempts to generate low energy [formula] scattering in the p(1,1) and p(3,3) states assuming the potential operating in these states is generated by the exchange of low mass meson states in the crossed t-channel and low mass baryon states in the crossed u channel. In particular, the p-meson is kept in channel t; the p mass and the coupling of [formula] and [formula] appear as parameters. The parameters of the nucleon and (3,3) poles are taken as the elements to be determined by self-consistency.
- 9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090
- The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format have been held as consistent as possible with 9-ZOOM, the companion one-dimensional program.
- 9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement]
- The following document describes the usage of the LRL 9-ZOOM code, a neutron diffusion theory reactor code for the IBM 709. The code has been modified to solve configuration of a series of stacked cylindrical disks, designating a new geometry case.
- 20-ton and 1/2-ton High Explosive Cratering Experiments in Basalt Rock: Final Report, August 1962
- This report describes the Sandia Corporation participation and results related to Project Buckboard: the detonation of three 40,000-pound and ten 1000-pound high-explosive charges in basalt rock to establish depth -of-burst curves.
- 20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962
- From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
- 30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System
- Final design for the 30 megawatt intermediate heat exchanger and steam generator.
- 30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis
- Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
- 30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures
- Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
- 80" Bubble Chamber Expansion System Preliminary Operating Procedures
- These procedures are intended to be used for the initial operation of the expansion system and serve as a basis for a more complete and revised form to be written once operating experience has been gained. An attempt has been made to offer a logical and systematic presentation to facilitate operation and maintenance of the system by the operating personnel. Thus, the sequence of valve actuations has been presented in matrix and check list form to minimize errors; this also has the advantage of making it easier to adapt certain expansion system procedures to programmed control by a process control computer.
- 80" Bubble Chamber Expansion System Summary of Piston Motion Studies
- Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and the other during the week of Nov. 12. The system was run with helium gas supplied from AGS compressor room and the piston was operated at room temperature.
- 80" Chamber - Low Energy Beams
- One of the major, as well as first, decisions which must be taken on a large chamber is to decide on the direction of the magnetic field, i.e., vertical or horizontal. Either alternative has advantages and disadvantages ad it is the intention of this note to discuss these features.
- 100-N Decontamination Facility Design Guide.
- Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
- 200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation
- From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
- 300,000-KWE SGR Nuclear Power Plant of Current Technology
- Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
- 568 Report
- Final report for a grant contract documenting information about the scope of the project and results.
- 1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
- From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
- 1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
- From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
- 1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
- From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1
- From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description
- From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept II System Description
- From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept II description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On-Study Program."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description
- From introduction: "The third of four designs to be developed by Babcock & Wilcox (B&W), Concept III observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description
- From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
- A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations
- An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
- A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method
- An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
- The 1958 He4 Scale of Temperatures: Part 1. Introduction, Part 2. Tables for the 1958 Temperature Scale
- Report containing information regarding He4 vapor pressure measurement as of 1958, the recent history of the vapor pressure temperature scale, and a series of tables containing these measurements.
- The 4K ANGIE Code
- The ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for 1 to 26 energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane.
- 6144-Channel Time-of-Flight Analyzer
- Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
- 630A Maritime Nuclear Steam Generator Scoping Study
- From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.
- 630A Maritime Nuclear Steam Generator: Status Report Number 1
- From foreword: The primary purpose of this document is to set forth the current status of the 630A Nuclear Steam Generator, under development for the U.S. AEC.
- The A.A.E.C. Atmospheric Pressure Heat Transfer Rigs
- This technical report describes two atmospheric pressure rigs with associated equipment designed for investigating heat transfer and friction characteristics of different type of "roughened" surfaces to develop suitable surfaces for an H.T.G.C.R. fuel element. Operating details are given together with techniques used to measure heat transfer and friction on a surface assembly incorporating selected "roughened" surfaces. Methods for calculating Stanton numbers, friction factors, and Reynolds numbers for such an assembly are included.
- ABCC-NIH Adult Health Study Hiroshima 1958-60. Cardiovascular Project Report Number 6, Heart Size Norm
- Data on 13,000 person 15 yr of age or older obtained during detailed clinical examinations, including radiological recorded heart size, were correlated with sex, age, height, and weight of subjects to arrive at a standard heart size for Hiroshima residents This information will be used in investigations cardiovascular disease in the population.
- Abscissas and Weights for Guassian Quadrature For N=2 to 100, and N-125, 150, 175, 200
- The abscissas and weights for Gaussian Quadrature of order N = 2 to 100,and N = 125, 150, 175, and 200 are given. The abscissas are given to twenty-four places and the error is estimated to be no more than 1 unit in the last place. The weights are given to twenty-three places and the error is estimated to be no more than 1 unit in the last place.
- Abscopal Effects of Localized Irradiation by Accelerator Beams
- The aim of this series of experiments was to evaluate the existence of abscopal effects of irradiation. No attempt was made towards the elucidation of mechanisms. Very early in the history of radiological research it was noticed radiation produces both local and general effects involving the entire body. Gauss and Lembcke introduced the term "Roentgenkater" (radiation sickness). They ascribed these "General Effects" to the circulation of toxic substances released from cells that disintegrated following irradiation.
- The Absolute Abundance of the Chromium Isotopes in Some Secondary Minerals
- From abstract: "Isotopic assays have been made on the chromium in samples from fourteen different chrominiferous minerals from different geographic and meteoritic sources. The results of the assays indicate that it is not possible to unequivocally state that variations in isotopic compositions have been observed."
- Absorption and Turnover Rates of Iron Measured by the Whole Body Counter
- Human iron metabolism has been extensively studied in the past twenty-five years with the radioisotopes iron⁵⁵ and iron⁵⁹. Before the availability of the whole body counter, however, iron absorption studies were performed by the indirect methods of fecal assay of unabsorbed radioiron, and estimation of red cell incorporation of absorbed tracer. The few long-term excretion studies performed required numerous assumptions, since human iron excretion was less well understood. Whole body counting provides a simple and accurate method of measuring the total body retention of administrative tracer iron⁵⁹, thus making absorption and subsequent excretion determinations possible with a single radioiron study. The energetic gamma emissions of iron⁵⁹ permit ready external detection with small quantities of isotope, Normal radioiron distribution is uniform throughout the circulating red cell mass and thus minimize geometry influences on the counting efficiency, 0nly the 45.1 day half-life of iron⁵⁹ limits long term iron turnover studies. Measurements of iron⁵⁹ absorption and long-term body turnover have been under way at Brookhaven National Laboratory for over two years. The present paper outlines some of the results of these studies, and discusses some implications of the method.
- Absorption-Multistage Flash Distillation Process
- "The major factors which influence the cost of water production from sea water by distillation methods are (1) the cost of fuel or energy required by the distilling plant, and (2) the required capital investment. Preliminary studies on the application of absorption or solution cycles to distillation methods for saline water conversion indicated that the fuel cost or thermal economy of a distillation plant could be improved by combining the distillation process with an absorption or solution cycle" (p. 1).
- 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.
- ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961
- Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
- ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962
- Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
- Acceleration Due to Gravity at the National Bureau of Standards
- Report describing the determination of the absolute value of the acceleration due to gravity at the National Bureau of Standards.
- Acceleration of Deuterons or Alpha Particles in the AGS
- The magnetic field of the AGS ring can contain particles of magnetic rigidity about 34 Bv/c. This includes not only protons of kinetic energy 33 Bev, but also 32 Bev deuterons, 64 Bev alpha particles, and conceivably heavier nuclei such as 188 Bev carbon nuclei. It will be shown in this paper that such nuclei can be injected and accelerated in the AGS if some rather small modifications are made in the injection and acceleration systems. What physics could be done with such beams? Several types of experiments may be suggested. In the first place, since the deuteron is a rather loosely bound combination of a neutron and a proton, it is likely to break up when it hits a target nucleus (stripping reaction). In a considerable fraction of the collisions the neutron will go straight on with essentially unchanged energy (half the deuteron energy). Therefore, with an internal target bombarded by 30 Bev deuterons one should obtain an intense, rather well collimated and monochromatic beam of 15 Bev neutrons in the forward direction.
- Acceleration of Polarized Protons to Relativistic Energies
- Maintenance of polarization of polarized protons in a linear accelerator is known to be feasible. Circular accelerators present a different problem, and the investigation of the interaction of orbit dynamics and particle polarization in general is undertaken. The equation of motion of the spin vector of a charged particle in a magnetic field as formulated by Bargmann, Michel, and Telegdi is utilized in the study of depolarization for several accelerators. High values of depolarization are obtained, and means for avoiding such depolarization are suggested. (D.C.W.)
- Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates
- The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.
- Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)
- 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; 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: Fourth Quarterly Progress Report September-November, 1962
- Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.
- Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)
- 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.