Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992
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The event Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992 represents a publication, printing, distribution, issue, release or production of resources found in Indiana State Library.
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Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992
Resource Information
The event Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992 represents a publication, printing, distribution, issue, release or production of resources found in Indiana State Library.
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- Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992
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- 1992
23 Items that share the ProviderEvent Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992
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Context of Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992Publication of
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- Accelerated irradiation test of Gundremmingen reactor vessel trepan material, prepared by J.R. Hawthorne
- Aging assessment of BWR standby liquid control systems, prepared by G.D. Buckley ... [and others]
- Aging assessment of bistables and switches in nuclear power plants, prepared by B.S. Lee, M. Villaran, M. Subudhi
- Aging assessment of component cooling water systems in pressurized water reactors, prepared by R. Lofaro ... [and others]
- Aging assessment of reactor instrumentation and protection system components : aging-related operating experiences, prepared by A.C. Gehl, E.W. Hagen
- Aging data analysis and risk assessment : development and demonstration study, prepared by A.J. Wolford, C.L. Atwood, W.S. Roesener
- Approaches for age-dependent probabilistic safety assessments with emphasis on prioritization and sensitivity studies, prepared by W.E. Vesely
- Comprehensive aging assessment of circuit breakers and relays, prepared by J.F. Gleason
- Constraint effects on fracture toughness for circumferentially oriented cracks in reactor pressure vessels, prepared by B.R. Bass, D.K. Shum, J. Keeney-Walker
- Evaluation of MHTGR fuel reliability, prepared by R.P. Wichner, W.P. Barthold
- Evaluation of behavior and the radial shear strength of a reinforced concrete containment structure, prepared by H.P. Walther
- Experimental and analytical investigation of the shallow-flaw effect in reactor pressure vessels, prepared by T.J. Theiss, D.K. Shum, S.T. Rolfe
- Experimental results of tests to investigate flaw behavior of mechanically loaded stainless steel clad plates, prepared by S.K. Iskander ... [and others]
- Fracture-mechanics-based failure analysis, prepared by A.R. Rosenfield, C.W. Marschall
- Functional capability of piping systems, D. Terao, E.C. Rodabaugh
- Gradient study of a large weld joining two forged A 508 shells of the Midland reactor vessel, prepared by G.R. Irwin, X.J. Zhang
- Improvements in motor operated gate valve design and prediction models for nuclear power plant systems : SBIR Phase I final report, September 1990-April 1991, prepared by J.K. Wang, M.S. Kalsi
- Insights gained from aging research, prepared by D.E. Blahnik ... [and others]
- Motor-operated valve research update, prepared by R. Steele, Jr... [and others]
- NRC research program on plant aging : listing and summaries of reports issued through July 1992, N.N. Kondic
- Review of reactor pressure vessel evaluation report for Yankee Rowe nuclear power station (YAEC no. 1735), prepared by R.D. Cheverton ... [and others] ; contributing authors, D.P. Bozarth .. [and others].
- Theoretical and user's manual for pc-PRAISE : a probabilistic fracture mechanics computer code for piping reliability analysis, prepared by D.O. Harris ... [and others]
- Verification of nonlinear piping response calculation with data from seismic testing of an in-plant piping system, prepared by M.G. Srinivasan, M. Mojtahed, C.A. Kot
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<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.library.in.gov/resource/XFyjkwgQxro/" typeof="PublicationEvent http://bibfra.me/vocab/lite/ProviderEvent"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/XFyjkwgQxro/">Washington, DC, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1992</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.library.in.gov/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.library.in.gov/">Indiana State Library</a></span></span></span></span></div>
