"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."

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

A final report regarding a Multiloop Integral System Test, or MIST.

"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."

A report regarding the results of a PBF severe fuel damage test

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.

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

Report describing small-scale laboratory experiments using a Beckman model 7C thermal conductivity cell conducted in order to provide a better understanding of the response of the hydrogen monitor during Power Burst Facility (PDF) Severe Fuel Damage (SFD) tests (p. 1).

"A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented"

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

"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)

"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 report presents, in considerable detail, the experimental data for the B-5 test conducted by the Multirod Burst Test (MRBT) Program at Oak Ridge National Laboratory."

A report regarding experiment data for a multirod burst test, to investigate cladding deformation in the alpha-plus-beta-Ziracloy temperature range under light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions."

"This report is the last in a series by the New York State Geological Survey on studies funded by the U.S. Nuclear Regulatory Commission. The report covers five important aspects of the geology and hydrology of the Western New York Nuclear Service Center, near West Valley, New York: geomorphology, stratigraphy, sedimentology, surface water, and radionuclide analyses. We reviewed past research on these subjects and present new data obtained in the final phase of NYSGS research at the site. Also presented are up-to-date summaries of the present knowledge of geomorphology and stratigraphy."

A parametric analysis regarding PWR pressure vessel integrity during overcooking accidents.

"The objective of this study is to provide an up-to-date documentation of the costs of nuclear electrical generating plants as they relate to site characteristics, in the following areas and systems: Main condenser cooling systems, Transmission, Site access, Food Protection, Plant site earthwork."

Graphs plotting the thermal-hydraulic response of the TC-1 tests characterized by the system depressurization, volumetric flow, temperature (in Kelvin) over time within each fuel rod flow shroud used in the study.