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Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs

Description: "The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was entitled in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking."
Date: October 1991
Creator: Hutton, P. H.; Kurtz, R. J.; Friesel, M. A.; Skorpik, J. R. & Dawson, J. F.
open access

Compilation, Assessment and Expansion of the Strong Earthquake Ground Motion Data Base: Seismic Margins Research Program (SSMRP)

Description: 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.
Date: September 1980
Creator: Crouse, C. B.; Hileman, J. A.; Turner, B. E. & Martin, G. R.
open access

Cost of NEPA Alternatives

Description: "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."
Date: August 1981
open access

Evaluation of trench subsidence and stabilization at Sheffield low-level radioactive waste disposal facility : Sheffield, Illinois, final report, October 15, 1980-March 30, 1981

Description: "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."
Date: May 1981
Creator: Kahle, R. & Rowlands, J.
open access

Experiment Data Report for Test RIA 1-2

Description: "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."
Date: June 1979
Creator: Zimmermann, Carolyn L.; White, Christine E. & Evans, Robert P.
open access

FRAPCON-2 : A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods

Description: 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.
Date: January 1981
Creator: Berna, Gary A.; Bohn, Michael P.; Rausch, W. N.; Williford, R. E. & Lanning, D. D.
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