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Oral History Interview with Odis Taylor, October 6, 1995

Description: Interview with Odis Taylor concerning his experiences before, during, and after his employment in the Civilian Conservation Corps during the Great Depression. Taylor worked at camps in Pierce, Idaho (Company 5702) and Emida, Idaho (Company 229).
Access: Restricted to UNT Community Members. Login required if off-campus.
Date: October 6, 1995
Creator: Ball, Paula & Taylor, Odis S.
Partner: UNT Oral History Program
captions transcript

[News Clip: Idaho-Fire]

Description: B-roll video footage from the KXAS-TV/NBC station in Fort Worth, Texas, to accompany a news story.
Date: July 29, 1995, 10:00 p.m.
Duration: 34 seconds
Creator: KXAS-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

Reactivity Initiated Accident Test Series Test RIA 1-4 Fuel Behavior Report

Description: "This report presents and discusses the results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory." from Abstract
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
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Appendix A. Test Design and Configuration

Description: "This appendix summarizes the design of the [Power Burst Facility] PBF test rods and test train hardware, and the rod assembly instrumentation" for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho. (p. A-2)
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
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Appendix B. Test Conduct

Description: This appendix describes the operational phases of the Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix C: Data Qualification, Uncertainties, and Data Plots

Description: "This appendix describes the Test RIA 1-4 data qualification procedures, methods for evaluating uncertainties, and detailed plots of qualified data." (p. C-2) The report discusses test design and configuration; test conduct; data qualification, uncertainties, and data plots; fuel rod analysis; pre- and post test nondestructive and destructive examination results; reactor physics analysis; and document and records traceability for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test… more
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix D. Fuel Rod Analysis

Description: Appendix providing analysis for fuel rod behavior for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
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Appendix E: Pre- and Postest Nondestructive and Desctructive Examination Results

Description: This appendix documents [nondestructive and destructive examinations and pretest data for for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test flow shroud removed after a test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix F: Reactor Physics Analysis

Description: Analysis for reactor physics for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix G: Document and Records Traceability

Description: "This appendix (a) provides a description of documentation and computer tapes generated while preparing for, conducing, and gathering data from Test RIA 1-4 at the Power Burst Facility (PBF); (b) provides a list of some primary documents; and (c) describes how to obtain finished data and some primary documents." (p. G-2)
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department

Appendix C. Qualified Data Plots

Description: Plots of qualified data from Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department

Plates 1-6: Uranium Favorability of Cenozoic Sedimentary Rocks of the Western Snake River Basin, Idaho

Description: Two maps showing the geologic features of the Western Snake River Basin, Idaho and locations of sample sites, wells, and cross-section locations. Four additional plates illustrate lithologic logs for the 17 petroleum test wells and 2 deep water wells selected for use in the study. The water wells were selected on the basis of total depth, quality of lithologic log, and location with respect to the lines of section. The sections A-A', B-B', C-C', and D-D' are shown on Plates 3 through 6, respect… more
Date: October 1976
Creator: Marjaniemi, Darwin Keith; Curry, William E. & Robins, Jerold W.
Partner: UNT Libraries Government Documents Department
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Aerial Radiometric and Magnetic Reconnaissance Survey of Portions of Arizona, Idaho, Montana, New Mexico, South Dakota and Washington: Final Report, Volume 1. Instrumentation and Methods

Description: From abstract: The objective of the work was to define areas showing surface indications of a generally higher uranium content where detailed exploration for uranium would most likely be successful.
Date: March 1979
Creator: Texas Instruments Incorporated
Partner: UNT Libraries Government Documents Department

[Appendix C-DARS Data Plots from Test SFD 1-3]

Description: Graphs showing plots of the qualified Power Burst Facility (PBF) Data Acquisition and Reduction System (DARS) data from Test Severe Fuel Damage (SFD) 1-3 performed at the Idaho National Engineering Laboratory. Qualified data is shown as a solid line and trend data appears as a dashed line.
Date: September 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-3 Concentration Data, Gasline]

Description: Scatter plots of isotopic concentrations from gasline detectors derived from Test Severe Fuel Damage (SFD) 1-3 gamma-ray spectral analysis showing measurement times(s) on the x-axis and concentration for each isotope on the y-axis.
Date: September 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-3 Concentration Data, Liquidline]

Description: Scatter plots of isotopic concentrations from liquidline detectors derived from Test Severe Fuel Damage (SFD) 1-3 gamma-ray spectral analysis showing measurement times(s) on the x-axis and concentration for each isotope on the y-axis.
Date: September 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
Partner: UNT Libraries Government Documents Department

[Appendix C-SFD 1-3 Concentration Data, Steamline]

Description: Scatter plots of isotopic concentrations from steamline detectors derived from Test Severe Fuel Damage (SFD) 1-3 gamma-ray spectral analysis showing measurement times(s) on the x-axis and concentration for each isotope on the y-axis.
Date: September 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
Partner: UNT Libraries Government Documents Department

[Appendix I-SCDAP/RELAP5 Analysis Model Code Calculations]

Description: Code calculations associated with Analysis of Test Severe Fuel Damage (SFD) 1-3 "performed with Quality Assured Version 251 of the SCDAP/RELAP5/MOD2 code, which is a computer code designed to characterize and quantify fuel damage processes in a reactor vessel during severe accidents. The code can be applied to the analysis of an individual fuel bundle, such as is the case for Test SFD 1-3, or to the analysis of an entire primary coolant system." (Page I-3 of the report)
Date: September 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
Partner: UNT Libraries Government Documents Department
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