Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991
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The event Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991 represents a publication, printing, distribution, issue, release or production of resources found in Indiana State Library.
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Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991
Resource Information
The event Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991 represents a publication, printing, distribution, issue, release or production of resources found in Indiana State Library.
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- Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991
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- 1991
10 Items that share the ProviderEvent Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991
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Context of Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991Publication of
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- A systematic approach to repetitive failures, prepared by D.J. Odland
- FORECAST : regulatory effects cost analysis software manual : version 3.0, prepared by B. Lopez, F.W. Sciacca, (microform)
- Ice-condenser aerosol tests, prepared by M.W. Ligotke, E.J. Eschbach, W.K. Winegardner
- MORECA, a computer code for simulating modular high-temperature gas-cooled nuclear reactor core heatup accidents, prepared by S.J. Ball
- New gamma-ray buildup factor data for point kernel calculations : ANS-6.4.3 standard reference data, prepared by D.K. Trubey
- Programmatic root cause analysis of maintenance personnel performance problems, prepared by K. Inaba
- Radionuclide characterization of reactor decommissioning waste and spent fuel assembly hardware : progress report, prepared by D.E. Robertson ... [and others]
- SPARC-90, a code for calculating fission product capture in suppression pools, prepared by P.C. Owczarski, K.W. Burk
- THATCH, a computer code for modelling thermal networks of high-temperature gas-cooled nuclear reactors, prepared by P.G. Kroeger ... [and others]
- VAM2D--variably saturated analysis model in two dimensions : version 5.2 with hysteresis and chained decay transport : documentation and user's guide, prepared by P.S. Huyakorn, J.B. Kool, Y.S. Wu
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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/RW4P4RyeE4c/" 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/RW4P4RyeE4c/">Washington, DC, Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission | Supt. of Docs., U.S. G.P.O. distributor, 1991</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>
