This report examines the adequacy of existing fire-hazards analysis methodology in the context of nuclear power plant safety

A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.

Analyses, interpretations, and discussions of results from the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-1, conducted in the Power Burst Facility reactor are presented.

Report discussing and comparing four techniques used for cladding temperatures achieved during Test RIA 1-1: metallorgraphic examination of cladding microstructures, computations based on isothermal oxidation kinetics, BUID5 computer code calculations, and weight gain calculations for metal-water reaction (p. 305)

"A summary of the experimental irradiation and energy deposition measurements of fuel enthalpy, useful in assessing the test fuel rod thermal history, is presented in this appendix." (p. 116)

Report presenting the results of the metallographic examination for Rods 801-1, 801-2, 801-3, and 801-5 used to supplement the visual inspection and posttest description of the Test RIA 1-1 fuel rods. (p. 177)

Tables, text, and diagrams describing the design, instrumentation, and assembly of fuel rods uses in Test RIA 1-1.

"The pretest characterization of the four Test RIA 1-1 fuel rods and flow shrouds is presented in this appendix." (p. 147)

Appendix to report discussing the SINGLE computer code used to determine radial fuel temperature profiles.

"This report presents and discusses the results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory." from Abstract

"This appendix summarizes the design of the [Power Burst Facility] PBF test rods and test train hardware, and the rod assembly instrumentation" for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho. (p. A-2)

This appendix describes the operational phases of the Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.

"This appendix describes the Test RIA 1-4 data qualification procedures, methods for evaluating uncertainties, and detailed plots of qualified data." (p. C-2) The report discusses test design and configuration; test conduct; data qualification, uncertainties, and data plots; fuel rod analysis; pre- and post test nondestructive and destructive examination results; reactor physics analysis; and document and records traceability for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.

Appendix providing analysis for fuel rod behavior for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.

This appendix documents [nondestructive and destructive examinations and pretest data for for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test flow shroud removed after a test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.

Analysis for reactor physics for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.

"This appendix (a) provides a description of documentation and computer tapes generated while preparing for, conducing, and gathering data from Test RIA 1-4 at the Power Burst Facility (PBF); (b) provides a list of some primary documents; and (c) describes how to obtain finished data and some primary documents." (p. G-2)

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.