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.

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."

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).

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).

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).

Printout from the INSITE (Information on Nuclear SITEs) Information System containing data related to user codes.

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.

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 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 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.

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.

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.

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