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.

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."

The following data presents stress value results from finite-element mesh studies described in its parent document, Stresses in Reinforced Nozzle-Cylinder Attachments Under External Moment Loadings Analyzed by the Finite-Element Method: A Parameter Study.

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).

Graphs showing power calibration and preconditioning data for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series 1, Test RIA 1-2. Results are presented for the time after the start of power calibration in hours for each variable (see pages ix - xi of report).

Power calibration and preconditioning data plots for PBF/LOFT Lead Rod Test Series, indicating the time after start of power calibration in hours with each variable.

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).

Graphs of data acquired from Instrumented Fuel Assembly 429 (IFA-429) for the period from June 1975 (beginning of life) to June 1978 (%17 100 MWd/t burnup).

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.

Plots of qualified data from Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.

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.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for onsite radiological accidents.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for background radiation dose rates.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data on ecology.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for site location and description, population and population distribution, nearby facilities and institutions, nearby land usage, nearby water usage, transportation systems and pipelines, and historic, cultural, scientific, scenic and wildlife areas.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for general geology and seismology, faulting and vibratory ground motion, and subsurface materials.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for surface waters, ground waters, water quality, floods, and low flows.