"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.

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.

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

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 presenting the results of nondestructive and destructive examinations of four fuel rods from Test RIA 1-2.

Report detailing the computer code used to calculate the cladding temperatures (WIZARD code) from the observed oxidation of the cladding for Test RIA 1-2.

This report presents and discusses the results from the Reactivity Initiated Accident Test RIA1-2 conducted in the Power Burst Facility at the Idaho National Engineering Laboratory.

Report listing the table of contents for appendices and figures included with the report: "Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report'

Graphs showing plots of the qualified Power Burst Facility (PBF) Data Acquisition and Reduction System (DARS) data from Test Severe Fuel Damage (SFD) 1-3 performed at the Idaho National Engineering Laboratory. Qualified data is shown as a solid line and trend data appears as a dashed line.

Scatter plots of isotopic concentrations from gasline detectors derived from Test Severe Fuel Damage (SFD) 1-3 gamma-ray spectral analysis showing measurement times(s) on the x-axis and concentration for each isotope on the y-axis.

Scatter plots of isotopic concentrations from liquidline detectors derived from Test Severe Fuel Damage (SFD) 1-3 gamma-ray spectral analysis showing measurement times(s) on the x-axis and concentration for each isotope on the y-axis.

Scatter plots of isotopic concentrations from steamline detectors derived from Test Severe Fuel Damage (SFD) 1-3 gamma-ray spectral analysis showing measurement times(s) on the x-axis and concentration for each isotope on the y-axis.

Code calculations associated with Analysis of Test Severe Fuel Damage (SFD) 1-3 "performed with Quality Assured Version 251 of the SCDAP/RELAP5/MOD2 code, which is a computer code designed to characterize and quantify fuel damage processes in a reactor vessel during severe accidents. The code can be applied to the analysis of an individual fuel bundle, such as is the case for Test SFD 1-3, or to the analysis of an entire primary coolant system." (Page I-3 of the report)

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

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).

Graphs showing plots of the qualified Power Burst Facility (PBF) Data Acquisition and Reduction System (DARS) data from Test Severe Fuel Damage (SFD) 1-4 performed at the Idaho National Engineering Laboratory. Qualified data is shown as a solid line and trend data appears as a dashed line (see page C-16 of report). Time (in seconds) appears on the x-axis and pressure (MPa) appears on the y-axis.

Scatter plots of isotopic concentrations from gasline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.

Scatter plots of isotopic concentrations from liquidline detectors derived from Test Severe Fuel Damage (SFD) 1-4 gamma-ray spectral analysis showing measurement time (in seconds) on the x-axis and concentration for each isotope on the y-axis.