A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.

This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corpoation, for the United States Department of Energy and the Nuclear Regulatory Commission, under DOE contract number DE-AC14-76FF02170 and NRC service request number TV-0176.

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."

"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."

WRAITH is a FORTRAN computer code which calculates the doses received by a standard man exposed to an accidental release of radioactive material

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."

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

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for project benefits, project and fuel alternative costs, and evaluation of alternatives.

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

"A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented"

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.

"A summary of the experimental irradiation and energy deposition measurements of fuel enthalpy, useful in assessing the test fuel rod thermal history, is presented in this appendix." (p. 116)

Report providing quantitative information of containment seismic capacity considering a rather complete list of limit states along with a discussion of factors that are significant for determining seismic capacity and recommendations for future work.

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

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.

A parametric analysis regarding PWR pressure vessel integrity during overcooking accidents.

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

SABRES II is an individual resolution computer simulation of combat between two small groups using small arms weapons.

"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."

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.

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

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for land use impacts, water use impacts, heat dissipation system impacts, nonradiological impacts on terrestrial ecosystems, nonradiological impacts on aquatic ecosystems, radiological impacts on biota other than man, radiological impacts on man, social and economic impacts, and transmission line impacts.

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.

Information collected from the United States Nuclear Regulatory Commission (USNRC) using the Information on Nuclear SITEs (INSITE) Information System. This document describes data for system characteristics, load and capacity, and consequences of delay.