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Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs

Description: "The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was entitled in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking."
Date: October 1991
Creator: Hutton, P. H.; Kurtz, R. J.; Friesel, M. A.; Skorpik, J. R. & Dawson, J. F.
Partner: UNT Libraries Government Documents Department

Appendix B: Software

Description: Dataset documenting the software programs used in the acoustic emission (AE) instruments systems developed under the U. S. Nuclear Regulatory Commission (NRC) / Pacific Northwest Laboratory (PNL) AE program.
Date: October 1991
Creator: Hutton, P. H.; Kurtz, R. J.; Friesel, M. A.; Skorpik, J. R. & Dawson, J. F.
Partner: UNT Libraries Government Documents Department

Bouguer Gravity Anomaly Map

Description: Bouguer gravity anomaly map derived from the data set and accompanying the report to document the data sources and the procedures used in the reduction of the data.
Date: October 1980
Creator: Keller, G. Randy; Russell, D. R.; Hinze, William J.; Reed, J. E. & Geraci, Philip J.
Location: None
Partner: UNT Libraries Government Documents Department
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Bouguer Gravity Anomaly Map of the East-Central Midcontinent of the United States: New Madrid Seismotectonic Study Group

Description: The purposes of this report are to document the data sources and the procedures used in the reduction of the data and to present a Bouguer gravity anomaly map derived from the data set.
Date: October 1980
Creator: Keller, G. Randy; Russell, D. R.; Hinze, William J.; Reed, J. E. & Geraci, Philip J.
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: October 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: October 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: October 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: October 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: October 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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