"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."

"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."

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

Dynamic test data from an experiment conducted to determine the puncture resistance of lead- and uranium-backed type AISI 316 stainless steel (SS) plates. The data is presented in line graphs. The parameters that were varied in this investigation were punch diameter, test plate thickness, backing material, and test temperature.

An errata sheet for geomorphic and erosion studies at the Western New York Nuclear Service Center West Valley, New York.

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

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."

"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 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.

"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."

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

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 Test PCM-4 of the Power-Cooling-Mismatch Test Series.

This report presents the results of the first three power-cooling-mismatch tests - Tests 8-1 RS CHF Scoping, and 8-1 RF - performed in the PCM Test Series.

This report presents the analysis of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch Test Series.

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

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for onsite radiological accidents.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for background radiation dose rates.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data on ecology.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for site location and description, population and population distribution, nearby facilities and institutions, nearby land usage, nearby water usage, transportation systems and pipelines, and historic, cultural, scientific, scenic and wildlife areas.