The following data provides the code for the SABRES II model.

The following data is a code listing and sample case output calculating the steady state thermal-mechanical behavior of oxide fuel rods.

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.

Document listing code calculations used for SCDAP/RELAP5 models, which has been designed to characterize fuel damage processes in a reactor vessel during severe accidents (see pages J-1 to J-4 of report).

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.

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.

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.

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.

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.

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)

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.

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.

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.

Computer printout listings of three data tables (Digitized Accelerogram, Recording Station, and Earthquake) organized alphabetically by country.

Appendix presenting postest bundle and individual fuel rod photographs for report "Test PCM-5 Fuel Rod Materials Behavior."

Charts analyzing Multirod Burst Test (MRBT) Bundle B-5 test data produced at Oak Ridge National Laboratory.

Sample input and output data from a linear elastic finite element computer program (NOZ-FLAW).

Tables presenting the results of COPS computer model analyses, which has been used to estimate local law enforcement agency (LLEA) officer availability in the neighborhood of 60 selected nuclear reactor sites. The tables show the unrestricted response and restricted response for both state and local police within a given radius for each neighborhood in the study (see page 10 of report).

The following data contains the line printer output for the terminal session for sample run #2 as described in its parent document, WRAITH: a Computer Code for Calculating Internal and External Doses Resulting From an Atomospheric Release of Radioactive Material.

Computer-generated graphical and tabular presentations of transient test and posttest deformation data for Multirod Burst Test (MRBT) Bundle B-6 (see pages 131-141 of report). "The primary objective of this 8 x 8 multirod burst test was to investigate cladding de-formation in the alpha-plus-beta-Zircaloy temperature range under simulated light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions. B-6 test conditions simulated the adiabatic heatup (reheat) phase of an LOCA and produced very uniform temperature distributions." - from Abstract

Dynamic test data from an experiment conducted to determine the puncture resistance of lead- and uranium-backed type AISI 316 stainless steel (SS) plates. The data is presented in line graphs. The parameters that were varied in this investigation were punch diameter, test plate thickness, backing material, and test temperature.

Graphical presentations of data from the 1/5-scale Mark I BWR Pressure Suppression Experiment (PSE) air transient tests, including HVLF Characterization Data, Impulse Characterization, Computed Load Cell Response Histories and Frequency Analyses, and Enthalpy Flux Evaluation (see Table E-1. Summary of microfiche descriptions)

Graphs presenting a summary of data for a fracture-mechanics parametric-type study conducted for a number of postulated transients, including critical fluences, pressures, and crack depth.

Tables detailing aging tallies produced as part of the aging failure survey. The tables display the detailed breakdown for the data by component, system effect, failure category, and age of component at the time of failure. (p. E-3 of report).