Scientific Computing Division FY-81 Cyber Rates and NOS/BE Scheduler Modifications

The following data is a code listing and sample case output calculating the steady state thermal-mechanical behavior of oxide fuel rods.
Date: January 1981
Creator: unknown
Object Type: Dataset
System: The UNT Digital Library
Appendix E. Post Irradiation Examination Results (open access)

Appendix E. Post Irradiation Examination Results

Report presenting the results of nondestructive and destructive examinations of four fuel rods from Test RIA 1-2.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Object Type: Report
System: The UNT Digital Library
Appendix F. Wizard Code (open access)

Appendix F. Wizard Code

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
Object Type: Report
System: The UNT Digital Library
[Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report: Appendix Table of Contents] (open access)

[Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report: Appendix Table of Contents]

Report listing the table of contents for appendices and figures included with the report: "Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report'
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Object Type: Report
System: The UNT Digital Library
Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report (open access)

Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report

This report presents and discusses the results from the Reactivity Initiated Accident Test RIA1-2 conducted in the Power Burst Facility at the Idaho National Engineering Laboratory.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Object Type: Report
System: The UNT Digital Library
FRAPCON-2 : A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods (open access)

FRAPCON-2 : A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods

FRAPCON-2 is a FORTRAN IV computer code that calculates the steady state response of light Mater reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, deformation, and tai lure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (a) heat conduction through the fuel and cladding, (b) cladding elastic and plastic deformation, (c) fuel-cladding mechanical interaction, (d) fission gas release, (e} fuel rod internal gas pressure, (f) heat transfer between fuel and cladding, (g) cladding oxidation, and (h) heat transfer from cladding to coolant. The code contains necessary material properties, water properties, and heat transfer correlations. FRAPCON-2 is programmed for use on the CDC Cyber 175 and 176 computers. The FRAPCON-2 code Is designed to generate initial conditions for transient fuel rod analysis by either the FRAP-T6 computer code or the thermal-hydraulic code, RELAP4/MOD7 Version 2.
Date: January 1981
Creator: Berna, Gary A.; Bohn, Michael P.; Rausch, W. N.; Williford, R. E. & Lanning, D. D.
Object Type: Report
System: The UNT Digital Library
Appendix B. Pretest Fuel Rod Charactization Data (open access)

Appendix B. Pretest Fuel Rod Charactization Data

Report presenting the pretest fuel rod characterization data for four rods used in Test RIA 1-2.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Object Type: Report
System: The UNT Digital Library
Appendix D. Energy Deposition Measurements (open access)

Appendix D. Energy Deposition Measurements

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
Object Type: Report
System: The UNT Digital Library
Appendix C. Power Burst Facility Design and Capabilities (open access)

Appendix C. Power Burst Facility Design and Capabilities

Report providing a detailed description of the Power Burst Facility (PBF) design and capabilities, including an illustration of the axial cross section of the PBF in-pile tube.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Object Type: Report
System: The UNT Digital Library
Appendix A. Design and Test Conduct (open access)

Appendix A. Design and Test Conduct

Report summarizing the design of Power Burst Facility (PBF) test rods, test train hardware, the individual rod assembly instrumentation, and test conduct.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Object Type: Report
System: The UNT Digital Library