0-2 kv Flash Tube Supplies (open access)

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.
Date: March 15, 1962
Creator: Miller, D. M.
Object Type: Report
System: The UNT Digital Library
6 kv Capacitor Charging Supply (open access)

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.)
Date: March 15, 1962
Creator: Miller, D. M.
Object Type: Report
System: The UNT Digital Library
An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation (open access)

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.
Date: May 1964
Creator: Sarkissian, M. Der
Object Type: Report
System: The UNT Digital Library
9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090 (open access)

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.
Date: October 28, 1960
Creator: Stone, Stuart P.
Object Type: Report
System: The UNT Digital Library
9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement] (open access)

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.
Date: July 12, 1960
Creator: Stone, S. P.
Object Type: Report
System: The UNT Digital Library
20-ton and 1/2-ton High Explosive Cratering Experiments in Basalt Rock: Final Report, August 1962 (open access)

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.
Date: August 1962
Creator: Vortman, L. J.; MacDougall, H. R. & Rauber, D. F.
Object Type: Report
System: The UNT Digital Library
20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962 (open access)

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.
Date: March 1960
Creator: Vortman, Luke J. & MacDougall, H. R.
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date: January 31, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

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.
Date: February 28, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

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.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
80" Bubble Chamber Expansion System Preliminary Operating Procedures (open access)

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.
Date: January 7, 1964
Creator: Goodzeit, C. L.
Object Type: Report
System: The UNT Digital Library
80" Bubble Chamber Expansion System Summary of Piston Motion Studies (open access)

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.
Date: January 7, 1964
Creator: Goodzeit, C. L.
Object Type: Report
System: The UNT Digital Library
80" Chamber - Low Energy Beams (open access)

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.
Date: January 3, 1964
Creator: Rau, R. R.
Object Type: Report
System: The UNT Digital Library
100-N Decontamination Facility Design Guide. (open access)

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.
Date: March 8, 1960
Creator: Bainard, W. D.
Object Type: Report
System: The UNT Digital Library
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation (open access)

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.
Date: 1965
Creator: North American Aviation. Atomics International Division.
Object Type: Report
System: The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology (open access)

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.
Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Object Type: Report
System: The UNT Digital Library
568 Report (open access)

568 Report

Final report for a grant contract documenting information about the scope of the project and results.
Date: 1960
Creator: Pollard, Ernest C. (Ernest Charles), 1906-1997
Object Type: Report
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1 (open access)

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."
Date: February 14, 1964
Creator: General Electric Company
Object Type: Report
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2 (open access)

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."
Date: February 14, 1964
Creator: General Electric Company
Object Type: Report
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3 (open access)

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."
Date: February 14, 1964
Creator: General Electric Company
Object Type: Report
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1 (open access)

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."
Date: June 1967
Creator: Goulding, B. J.
Object Type: Report
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description (open access)

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."
Date: April 1967
Creator: Boyer, R. L.
Object Type: Report
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept II System Description (open access)

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."
Date: June 1967
Creator: Goulding, B. J.
Object Type: Report
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description (open access)

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."
Date: July 1967
Creator: Goulding, B. J.
Object Type: Report
System: The UNT Digital Library