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.

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)

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.

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

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.

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

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.

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

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

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.

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.

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 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.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for plant identification, unit status, and project permits and licenses.

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

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for project benefits, project and fuel alternative costs, and evaluation of alternatives.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for environmental design bases, external appearance, reactor systems, steam-electric system, heat dissipation system, cooling water intake and discharge systems, radwaste systems, chemical and sanitary waste systems, transmission facilities, and transportation connections.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for land use impacts, water use impacts, impacts on terrestrial ecological systems, impacts on aquatic ecological systems, social and economic impacts, and transmission line impacts.

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 land use impacts, water use impacts, heat dissipation system impacts, nonradiological impacts on terrestrial ecosystems, nonradiological impacts on aquatic ecosystems, radiological impacts on biota other than man, radiological impacts on man, social and economic impacts, and transmission line impacts.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for system characteristics, load and capacity, and consequences of delay.