Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 9 (T3009AA): cold leg discharge leak.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 8 (T300806): pumps operating.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 7 (T3007CC): lowered SG levels.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 5 (T300504): RVVVs closed.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 6, (T300605): Unequal SG Levels

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 4 (T3004CC): No HPI-Leak Cooling.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 3 (T3003AA): nominal - 5 cm2.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 1 (T3001BB): isolated pressurizer.

Dataset presenting a graphical representation of final testing data for multiloop integral system test (MIST) group 30 mapping test 0 (T300001): increase leak size.

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.

Graphs plotting selected response spectrums from seismic analysis models.

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).

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.

"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)

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 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.

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 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.

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 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)

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)

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).

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.

Scatter plots of isotopic concentrations from steamline 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.