"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.

Graphs presenting peak power history, ratio of local rod power to rod average power (P/A), total heat transfer coefficient history, and coolant pressure history conditions in the test assembly during the transient phase of the TC-1 tests.

Tables presenting design variables for TC-1 fuel rods including composite powder analysis, pellet and fuel stack dimensions, and fuel rod and flow shroud dimensions.

Report presenting the design of the Test TC-1 test train and Power Burst Facility (PBF) blowdown system and the test conduct in tables, text, and illustrations.

"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."

The objective of this program was to provide a mechanical-property database that could be used to predict the performance of Zircaloy cladding under various off-normal, transient, and accident conditions in a power reactor.

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

"This report presents the results of the evaluation of trench subsidence and possible future stabilization techniques at the Sheffield Low-Level Radioactive Waste Disposal Facility, Sheffield, Illinois."

The results of an in-pile nuclear blowdown test series, designated TC-1, are presented in this report.

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."

Computer printout listings of three data tables (Digitized Accelerogram, Recording Station, and Earthquake) organized alphabetically by country.

The compilation, assessment, and expansion of the Strong Earthquake Ground Motion Data Base.

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

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

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 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.

FRAPCON-2 is a FORTRAN IV computer code that calculates the steady state response of light Mater reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, deformation, and tai lure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (a) heat conduction through the fuel and cladding, (b) cladding elastic and plastic deformation, (c) fuel-cladding mechanical interaction, (d) fission gas release, (e} fuel rod internal gas pressure, (f) heat transfer between fuel and cladding, (g) cladding oxidation, and (h) heat transfer from cladding to coolant. The code contains necessary material properties, water properties, and heat transfer correlations. FRAPCON-2 is programmed for use on the CDC Cyber 175 and 176 computers. The FRAPCON-2 code Is designed to generate initial conditions for transient fuel rod analysis by either the FRAP-T6 computer code or the thermal-hydraulic code, RELAP4/MOD7 Version 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'

The following data is a code listing and sample case output calculating the steady state thermal-mechanical behavior of oxide fuel rods.