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|a (TOE)ost1083818
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|a (TOE)1083818
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|a E 1.99:pnl-3810-3
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|a pnl-3810-3
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|a Reactor Safety Research Programs Quarterly Report July - September 1981
|h [electronic resource]
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| 260 |
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|a Richland, Wash. :
|b Pacific Northwest National Laboratory (U.S.) ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1982.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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| 337 |
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through SciTech Connect.
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|a 01/01/1982.
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|a "pnl-3810-3"
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|a Edler, S. K.
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| 500 |
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|a Office of Nuclear Regulatory Research.
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|a This document summarizes the work performed by Pacific Northwest laboratory (PNL) from July 1 through September 30, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR} steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.
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|b DE-AC06-76RL01830.
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| 650 |
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7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
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| 650 |
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|a Engineering.
|2 edbsc.
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|a Materials Science.
|2 edbsc.
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|a Pacific Northwest National Laboratory (U.S.).
|4 res.
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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|u http://www.osti.gov/scitech/biblio/1083818
|z Online Access
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|a .b74056864
|b 03-07-23
|c 07-05-13
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| 998 |
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|a web
|b 09-09-16
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| 952 |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:pnl-3810-3
|h Superintendent of Documents classification
|i web
|n 1
|
