Report presenting the pretest physical characterization data for the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1 fuel rod for use in model evaluation and posttest comparison. (p. 78)

Report presenting the results of power calibration measurements and radiochemical analysis used to analyze and interpret Power-Cooling-Mismatch (Test PCM-4) data.

Report providing estimates of instrument calibration and data system acquisition errors as well as the equation for estimating 95% confidence levels for transducers and the surveillance system for the Power-Cooling-Mismatch (Test PCM-4).

This report presents the fuel rod behavior results of the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1.

Report presenting data plots for selected parameters measured during Test PCM-4 of the Power-Cooling-Mismatch Test Series.

The following data presents stress value results from finite-element mesh studies described in its parent document, Stresses in Reinforced Nozzle-Cylinder Attachments Under External Moment Loadings Analyzed by the Finite-Element Method: A Parameter Study.

Charts analyzing Multirod Burst Test (MRBT) Bundle B-5 test data produced at Oak Ridge National Laboratory.

"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."

Sample input and output data from a linear elastic finite element computer program (NOZ-FLAW).

From Abstract. "This report describes a linear elastic finite element computer program (NOZ-FLAW) which is used for the direct evaluation of mixed-mode stress intensity factors (K1, KII K111) along user-defined crack flaws at pressure-vessel nozzle corners." From Forward: "The work reported here was performed at the Oak Ridge National Laboratory and at the Georgia Institute of Technology under UCC-ND Subcontract No. 7565."

"Recorded test data are presented for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series 1, Test RIA 1-2. This Test, conducted at the Power Burst Facility, had the following objectives: (1) Characterize the response of preirradiated fuel rods during an RIA event conducted at boiling water reactor hot-startup conditions. (2) Evaluate the effect of rod internal pressure on preirradiated fuel rod response during an RIA event."

Graphs showing power calibration and preconditioning data for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series 1, Test RIA 1-2. Results are presented for the time after the start of power calibration in hours for each variable (see pages ix - xi of report).

A report discussing work performed at the Oak Ridge National Laboratory in support of the ORNL Design Criteria for Piping and Nozzle Program being conducted for the U.S. Nuclear Regulatory Research.

Power calibration and preconditioning data plots for PBF/LOFT Lead Rod Test Series, indicating the time after start of power calibration in hours with each variable.

This report presents recorded test data for Tests LLR-S0, LLR-3, LLR-4A, and LLR-5 of the thermal Fuels Behavior Program PBF/LOFT Lead Rod Test Series.

"The COPS computer model has been used to estimate local law enforcement agency (LLAE) officer availability in the neighborhood of selected nuclear reactor sites. The results of these analyses are presented both in graphic and tabular form in this report."

Tables presenting the results of COPS computer model analyses, which has been used to estimate local law enforcement agency (LLEA) officer availability in the neighborhood of 60 selected nuclear reactor sites. The tables show the unrestricted response and restricted response for both state and local police within a given radius for each neighborhood in the study (see page 10 of report).

Graphs of data acquired from Instrumented Fuel Assembly 429 (IFA-429) for the period from June 1975 (beginning of life) to June 1978 (%17 100 MWd/t burnup).

This report presents data acquired from Instrumental Fuel Assembly 429.

A report regarding results of an extended analysis of data from a 1/5-scale Mark I boiling water reactor pressure suppression experiment.

Report on the development of improved analytical methods for predicting puncture of radioactive material shipping containers.

"This report describes a systematic study to determine the relationship between seismicity and geologic or geophysical features for the central and eastern United States in order to delineate seismic hazard."

"This report presents results of the investigation to characterize the existing surface conditions at the Sheffield Low-Level Waste Disposal Facility Sheffield Illinois."

MAthematical-modeling studies were carried out to determine effects of isothermal and anisothermal anneals on recovery of mechanical properties of irradiated Zircaloy.