U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering
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The organization U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
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U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering
Resource Information
The organization U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
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- U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering
- Authority link
- (EG-IN)1176759
- Subordinate unit
-
- Office of Nuclear Reactor Regulation
- Division of Engineering
25 Items by the Organization U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering
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- A comparative analysis of special treatment requirements for systems, structures, and components (SSCs) of nuclear power plants with commercial requirements of non-nuclear power plants
- Aging assessment of safety-related fuses used in low- and medium-voltage applications in nuclear power plants
- Aging assessment of safety-related fuses used in low-and medium-voltage applications in nuclear power plants
- Ampacity derating and cable functionality for raceway fire barriers
- Analysis of bellows expansion joints in the Sequoyah containment
- Aquatic impacts from operation of three midwestern nuclear power stations
- Assessment of soil amplification of earthquake ground motion using the "CARES" code version 1.2
- BWR steel containment corrosion
- Buckling evaluation of System 80+ containment
- Consideration of uncertainties in soil-structure interaction computations
- Crack propagation in high strain regions of Sequoyah containment
- Effects of aging and service wear on main steam isolation valves and valve operators
- Effects of thermal aging on fracture toughness and charpy-impact strength of stainless steel pipe welds
- Examples, clarifications, and guidance on preparing requests for relief from pump and valve inservice testing requirements
- Operational experience and maintenance programs of Transamerica Delaval, Inc., diesel generators
- Reactor pressure vessel status report
- Reactor pressure vessel status report : [supplement 2]
- Revised Livermore seismic hazard estimates for sixty-nine nuclear power plant sites east of the Rocky Mountains : final report
- Seismic and dynamic qualification of safety related electrical and mechanical equipment
- Status report : intergranular stress corrosion cracking of BWR core shrouds and other internal components
- Steam generator operating experience update : 1984-86
- Steam generator operating experience, update for ..
- Summary of failure analysis activities at Brookhaven National Laboratory
- U.S. operating experience with thermally treated Alloy 600 steam generator tubes
- Year 2000 readiness in U.S. nuclear power plants
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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/JR9Y9RoxMfc/" typeof="Organization http://bibfra.me/vocab/lite/Organization"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/JR9Y9RoxMfc/">U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation | Division of Engineering</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>
