This regulatory guide lists those Section III ASME Code Cases oriented to materials and testing that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.
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This regulatory guide lists those Section XI ASME Code Cases that are generally acceptable to the NRC staff for implementation in the inservice inspection of light-water-cooled nuclear power plants.
This regulatory guide lists those Section III ASME Code Cases oriented to design and fabrication that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.
Section III ASME Code Cases oriented to design and fabrication of reactor coolant pressure boundary components that are generally acceptable to the NRC staff for implementation in the licensing of LWR plants are listed.
The regulatory guide lists those Section III ASME Code Cases oriented to reactor coolant pressure boundary component materials and testing that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.
The regulatory guide lists those Section III ASME Code Cases oriented to reactor coolant pressure boundary component design and fabrication that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.
A listing is given of those Section 3 ASME code cases oriented to materials and testing that are generally acceptable to the NRC staff for implementation in the licensing of light-water cooled nuclear power plants.
The regulatory guide presented lists those Section III ASME Code Cases oriented to reactor coolant pressure boundary component design and fabrication that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.
The paper presents a retrospective on the development and applications of fracture mechanics-based toughness requirements and flaw evaluation methodology in Sections III and XI of the ASME Code. Section III developments range from the rules and requirements for thick section Class 1 pressure vessels to thinner ...
Current activities of the American Society of Mechanical Engineers (ASME), Section III Subgroup on Containment Systems for Spent Fuel High-Level Waste Transport Packagings (also known as Subgroup NUPACK) are reviewed with emphasis on the recent revision of Subsection WB. Also, brief insightson new proposals for the development of rules for internal support ...
DOE Information Bridge
High level radioactive waste canisters are sealed by resistance upset welding to ensure leak tight closures. Resistance welding is fast, uniform, and can be performed remotely to minimize radiation exposure to the operators. Canisters are constructed in accordance with ASME Band PV Code, Section VIII, Division 1, however, the resistance welds are not used ...
... Accession Number : ADD341404. Title : Implementation of ASME Section XI Appendix VIII, Performance Demonstration Requirements,. ...
DTIC Science & Technology
... 10 CFR 50 WITH ASME SECTION XI, NRC REGULATORY GUIDES ... THE REGULATORY REQUIREMENTS OF THE US GOVERNMENT, CODES ...
Reference to ASME Section III, NB-2556 is no longer applicable. Reference changed to applicable material specification ASME SA-652 which now invokes ASME Section V and states evaluation requirements.
... TESTING CONSTITUTES AN IMPORTANT PART OF THE ASME BOILER AND PRESSURE VESSEL CODE. SECTION V DEALS EXCLUSIVELY ...
... Title : Nuclear Utility Implementation of ASME Code Section XI, Appendix VIII, Performance Demonstrations of Ultrasonic Examination Systems,. ...
... Accession Number : ADD333423. Title : Flawed Specimen Design and Manufacture for ASME Section XI, Appendix VII-VIII,. Corporate Author : ...
... Title : ASME Boiler and Pressure Vessel Code: Section X. Fiberglass- Reinforced Plastic Pressure Vessels. Addenda. Corporate ...
... Accession Number : ADD423256. Title : ASME Boiler and Pressure Vessel Code: Section X-Fiberglass-Reinforced Plastic Pressure Vessels. ...
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code was primarily written with stress-based acceptance criteria. These criteria are applicable to force, displacement, and energy-controlled loadings and ensure a factor of safety against failure. However, stress-based acceptance criteria are ...
This regulatory guide lists those Section XI ASME Code Cases that are generally acceptable to the NRC staff for implementation in the inservice inspection of light-water-cooled nuclear power plants. Any guidance in this document related to information collection activities has been cleared under OMB Clearance No. 3150-0011.
The guide delineates acceptable design limits and appropriate combinations of loadings associated with normal operation, postulated accidents, and specified seismic events for the design of Class 1 linear-type component supports as defined in Subsection NF of Section III of the American Society of Mechanical Engineers (ASME) Boiler and ...
The guide delineates acceptable design limits and appropriate combinations of loadings associated with normal operations, postulated accidents, and specified seismic events for the design of Class 1 linear-type component supports as defined in Subsection NF of Section III of the American Society of Mechanical Engineers (ASME) Boiler ...
A preliminary study was initiated to evaluate the conservatism of existing design methods regarding cyclic loadings and crack growth in nuclear power plant components. The study was based on the assumption that the application of the ASME Boiler and Pressure Vessel Code (the Code) should be consistent throughout the design, operation, and inspection phases. Specifically, any ...
