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Investigations in the Fall Creek Area, Bonneville County, Idaho, During the 1952 Field Season: A Preliminary Report

Description: Introduction: Field work during the 1952 field season has supplied new data on the areal extent, composition, and estimated reserves of uranium-bearing carbonaceous rocks in the Fall Creek.area, Bonneville County, Idaho. The following is a preliminary report of progress to describe these new data which supplement the information contained in Trace Elements Memorandum Report 340 (Vine and Moore, 1952). This work was done on behalf of the Division of Raw Materials of the U. S. Atomic Energy Commi… more
Date: November 1952
Creator: Vine, James David
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Geology and Uranium Deposits in Carbonaceous Rocks of the Fall Creek Area, Bonneville County, Idaho

Description: From introduction: This report describes the general geologic setting, the occurrences of uranium or radioactivity in the Fall Creek, Idaho area and adjacent areas, the probable nature of the mineralization and origin of the deposits, and the estimated reserves of uranium-bearing rock.
Date: July 1954
Creator: Vine, James David
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Geology and Uranium Deposits in Carbonaceous Rocks of the Fall Creek Area, Bonneville County, Idaho

Description: Report discussing the geology and uraniferous carbonaceous rocks found in the Bear River of the Fall Creek area of Bonneville County, Idaho. The report provides information regarding the geology of the area, uranium occurrences, distribution of uranium and other elements in carbonaceous materials, origin of uranium occurrences, core drilling results, and inferred reserves.
Date: July 1954
Creator: Vine, James D.
open access

Operating Manual for the MTR, Section Two -- Exclusion Area, Materials Testing Reactor

Description: From summary: "This manual is designed for the purpose of clarifying operating procedures of the Materials Testing Reactor and its associated equipment. In assembling this manual a description of each item of equipment and its function is presented. In addition, the generally accepted method of operating the equipment and the best corrective measures concerning all emergencies that might be encountered are set forth herein. Descriptive drawings and written instructions pertaining to the equipme… more
Date: 1955
Creator: Phillips Petroleum Company. Atomic Energy Division.

[Appendix C-SFD 1-4 Concentration Data, Main Floor]

Description: Scatter plots of isotopic concentrations from main floor detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
open access

The Beckman 7C Thermal Cell (Hydrogen Monitor) Experiments

Description: Report describing small-scale laboratory experiments using a Beckman model 7C thermal conductivity cell conducted in order to provide a better understanding of the response of the hydrogen monitor during Power Burst Facility (PDF) Severe Fuel Damage (SFD) tests (p. 1).
Date: April 1989
Creator: Petti, D. A.; Carboneau, M. L; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R. et al.

[Appendix C-SFD 1-4 Concentration Data, Steamline]

Description: Scatter plots of isotopic concentrations from steamline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.

[Appendix C-SFD 1-4 Concentration Data, Liquidline]

Description: Scatter plots of isotopic concentrations from liquidline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.

[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: October 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.

[Appendix C-SFD 1-4 Concentration Data, Gasline]

Description: Scatter plots of isotopic concentrations from gasline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.

[Appendix C-DARS Data Plots from Test SFD 1-4]

Description: Graphs showing plots of the qualified Power Burst Facility (PBF) Data Acquisition and Reduction System (DARS) data from Test Severe Fuel Damage (SFD) 1-4 performed at the Idaho National Engineering Laboratory. Qualified data is shown as a solid line and trend data appears as a dashed line (see page C-16 of report). Time (in seconds) appears on the x-axis and pressure (MPa) appears on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.

[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: October 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.

[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: October 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.

[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: October 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.

[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: October 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
open access

Appendix F. Wizard Code

Description: Report detailing the computer code used to calculate the cladding temperatures (WIZARD code) from the observed oxidation of the cladding for Test RIA 1-2.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
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Appendix D. Energy Deposition Measurements

Description: Report describing four different methods of measuring the total radially averaged fission energy deposited in PBF (Power Burst Facility) fuel rods, as well as a summary evaluation of each method.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
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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.
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