Report presenting the pretest fuel rod characterization data for four rods used in Test RIA 1-2.

Report describing four different methods of measuring the total radially averaged fission energy deposited in PBF (Power Burst Facility) fuel rods, as well as a summary evaluation of each method.

Report providing a detailed description of the Power Burst Facility (PBF) design and capabilities, including an illustration of the axial cross section of the PBF in-pile tube.

Report summarizing the design of Power Burst Facility (PBF) test rods, test train hardware, the individual rod assembly instrumentation, and test conduct.

"This report describes the methods, analyses, results, and conclusions of two different aging studies."

A report discussing a leak and structural test of a personal airlock, for LWR contaminants, subjected to pressures and temperatures beyond the design limits.

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).

Dataset including tabulations and plots for each active transducer used in nuclear containment tests 2A, 2B, 2C, 3A, 3B performed for a study of personal airlock door seals.

"In addition to BWR background information, this document contains a description of the experimental hardware with details on how the experiment was instrumented and diagnosed, a description of the test progression, and a presentation on the on-line instruments."

"The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was entitled in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking."

Graphs presenting measured data for the DF-4 control blade/channel box fuel damage experiment including a graphical representation of each of the on-line measured data quantities.

Eighteen electronic drawings detailing hardware from the sensor through the two console racks for the acoustic emission instrument system.

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.

Report providing quantitative information of containment seismic capacity considering a rather complete list of limit states along with a discussion of factors that are significant for determining seismic capacity and recommendations for future work.

Graphs plotting selected response spectrums from seismic analysis models.

A report regarding geophysical investigations of the Western Ohio-Indiana Region

"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

"The appendix contains daily and monthly tabulations of running time for each station" monitoring earthquake activity in the Western Ohio - Indiana region. (p. A1)

"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.