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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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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.

[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.

[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.
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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.

[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.

[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.

[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.

[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-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 1-4 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.

[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.
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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 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.
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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 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.

[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.
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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.
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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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