The Online Books Page

Nuclear power plants -- Piping -- Safety regulations

See also what's at your library, or elsewhere.

• Nuclear power plants -- Piping
• Nuclear power plants -- Safety regulations

• Nuclear power plants -- Piping -- Safety regulations -- Canada
• Nuclear power plants -- Piping -- Safety regulations -- France
• Nuclear power plants -- Piping -- Safety regulations -- Sweden
• Nuclear power plants -- Piping -- Safety regulations -- Switzerland
• Nuclear power plants -- Piping -- Safety regulations -- United States

• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by Canada, United States. 1987 Apr. 28, and United States Department of State (page images at HathiTrust)

• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by France, United States. 1987 Feb. 20, and United States Department of State (page images at HathiTrust)

• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by Sweden, United States. 1987 Feb. 2, and United States Department of State (page images at HathiTrust)

• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by Switzerland, United States. 1987 Feb. 3, and United States Department of State (page images at HathiTrust)

• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by Sweden, United States. 1987 Feb. 2, and United States Department of State (page images at HathiTrust)
• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by Switzerland, United States. 1987 Feb. 3, and United States Department of State (page images at HathiTrust)
• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by France, United States. 1987 Feb. 20, and United States Department of State (page images at HathiTrust)
• International Piping Integrity Research Group (IPIRG) (Dept. of State :, 1997), by Canada, United States. 1987 Apr. 28, and United States Department of State (page images at HathiTrust)

Items below (if any) are from related and broader terms.

• Investigation and evaluation of cracking incidents in piping in pressurized water reactors (U.S. Nuclear Regulatory Commission :, 1980), by U.S. Nuclear Regulatory Commission and PWR Pipe Crack Study Group (U.S.) (page images at HathiTrust)
• Recommended procedures and guidelines for analytical verification of liquid metal piping system response : topical report (Dept. of Energy, 1981), by K. L. Merz (page images at HathiTrust)
• A critical survey on the application of plastic fracture mechanics to nuclear pressure vessels and piping (Division of Reactor Safety Research, Office of Nuclear Regulatory Commission, U.S. Nuclear Regulatory Commission :, 1981), by Melvin F. Kanninen, David Broek, C. H. Popelar, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Pipe damping-results of vibration tests in the 33 to 100 hertz frequency range (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by Arthur G. Ware, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and EG & G Idaho (page images at HathiTrust)
• NRC leak-before-break (LBB.NRC) analysis method for circumferentially through-wall cracked pipes under axial plus bending loads : topical report (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by R. Klecker, G. M. Wilkowski, F. Brust, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Reactor primary coolant system pipe rupture study method for detection of sensitization in stainless steel (The Commission, 1965), by W. L. Clarke, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch, and General Electric Company. Nuclear Energy Engineering Division (page images at HathiTrust)
• Probability of pipe fracture in the primary coolant loop of a PWR plant (The Commission, 1981), by Stephen C. H. Lu, Lawrence Livermore Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Logarithmic spiral light pipe for scintaillators (Argonne National Laboratory, 1960), by William C. Kaiser, William W. Managan, Anthony J. Mackay, U.S. Atomic Energy Comission, and Argonne National Laboratory. Electronics Division (page images at HathiTrust)
• Two-phase pressure drop in piping components (Hanford Atomic Products Operation, 1964), by D. E. Fitzsimmons, U.S. Atomic Energy Commission. Dept. of Commerce, United States. Energy Research and Development Administration, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Materials testing reactor hot cell tests of high pressure piping (U.S. Atomic Energy Commission, Idaho Operations Office, 1956), by M. S. Robinson, M. H. Bartz, F. W. Rider, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Resolving time of the scintillation counter (Radiation Laboratory, University of California, 1952), by Richard F. Post, Lawrence Radiation Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of a variable orifice for Hallam Nuclear Power Facility fuel channels (Atomics International, 1961), by C. J. Baroczy, W. D. Leonard, J. A. Hagel, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Review and assessment of research relevant to design aspects of nuclear power plant piping systems : final report (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research ;, 1977), by E. C. Rodabaugh, R. J. Eiber, W. A. Maxey, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Suggested interim structural design criteria for the FTR primary piping system (Richland, Washington : Pacific Northwest Laboratory, 1969., 1969), by Marlyn T. Jakub, Battelle Memorial Institute. Pacific Northwest Division, U.S. Atomic Energy Commission, and Pacific Northwest Laboratory (page images at HathiTrust)
• Report of thermal cycle testing on sample pieces of stainless steel-lined carbon steel piping (San Jose, California : General Electric Company, Atomic Power Equipment Department, 1962., 1962), by P. J. Herbert, C. J. McDaniel, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• Pressure and thermal stresses at a pipe attachment to a sphere (Knolls Atomic Power Laboratory, General Electric Company, 1959), by Lorenzo Deagle, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Crack growth evaluation for small cracks in reactor coolant piping (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), by F. A. Simonen, D. Jones, T. P. Forte, M. E. Mayfield, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Design criteria for Piping and Nozzles Program quarterly progress report for ... (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Engineering Technology Division., in the 20th century), by Oak Ridge National Laboratory. Engineering Technology Division, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, United States. Energy Research and Development Administration, and Union Carbide Corporation (page images at HathiTrust)

• Review of methods and criteria for dynamic combination in piping systems (The Commission :, 1980), by M. Reich, Brookhaven National Laboratory. Department of Nuclear Energy, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)

• Proceedings of the Seminar on Leak-Before-Break : international policies and supporting research : held at Columbus, Ohio, October 28-30, 1985 (The Commission :, 1986), by Ohio) Seminar on Leak-Before-Break (1985 : Columbus, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)

• Prediction and mitigation of erosive corrosive wear in secondary piping systems of nuclear power plants. (The Commission, 1987), by R. G. Keck, P. Griffith, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Massachusetts Institute of Technology. Department of Mechanical Engineering (page images at HathiTrust)

• Mechanical design considerations in primary nuclear piping (U.S. Atomic Energy Commission, Division of Technical Information Extension, 1964), by S. W. Tagart, R. F. Gill, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The experimental determination of pipe reactions (Schenectady, New York : Knolls Atomic Power Laboratory, 1952., 1952), by W. E. Cooper, Knolls Atomic Power Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)

• Development of a testing and analysis methodology to determine the functional condition of solenoid operated valves (Divison of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by Richard D. Meininger, Thomas J. Weir, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Inc Pentek (page images at HathiTrust)
• An evaluation of piping analysis methods (Knolls Atomic Power Laboratory, General Electric Company, 1955), by K. L. Hanson, W. E. Jahsman, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)

• Analyses of the impact of inservice inspection using a piping reliability model (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1984., 1984), by F. A. Simonen, H. H. Woo, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)

• Design criteria for Piping and Nozzles Program quarterly progress report for ... (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Engineering Technology Division., in the 20th century), by Oak Ridge National Laboratory. Engineering Technology Division, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, United States. Energy Research and Development Administration, and Union Carbide Corporation (page images at HathiTrust)

• Experimental results from laboratory tests in the seismic range. (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by Arthur G. Ware, James G. Arendts, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and EG & G Idaho (page images at HathiTrust)

• Seismic Design and Evaluation Guidelines for the Department of Energy High-Level Waste Storage Tanks and Appurtenances (1995), by K. K. Bandyopadhyay, A. Cornell, C. Constantino, R. Kennedy, C. Miller, and A. S. Veletsos (PDF at osti.gov)

• Pressure vessel and piping codes applicable to the PWR reactor plant (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by J. F. Dobinsky, T. R. Moffette, M. B. Andrew, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)

• Modifications to SAP IV for seismic analyses of piping systems with multisupport input : topical report (Dept. of Energy, 1982), by Agbabian Associates (page images at HathiTrust)
• Development of a testing and analysis methodology to determine the functional condition of solenoid operated valves (Divison of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by Richard D. Meininger, Thomas J. Weir, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Inc Pentek (page images at HathiTrust)
• The Development of a plan for the assessment of degraded nuclear piping by experimentation and tearing instability fracture mechanics analysis (Washington, D. C. : Division of Nucelar Regulatory Research, U.S. Nuclear Regulatory Commission, 1983., 1983), by Melvin F. Kanninen, D. Broek, C. H. Popelar, E. R. Gilbert, C. W. Marschall, J. Ahmad, J. Pan, G. M. Wilkowski, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)

• Crack growth evaluation for small cracks in reactor coolant piping (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), by F. A. Simonen, D. Jones, T. P. Forte, M. E. Mayfield, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)

• Response of a 4-inch nuclear power plant valve to dynamic excitation (The Commission :, 1980), by S. F. Masri, S. J. Stott, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Response of a 6-inch nuclear power plant valve to dynamic excitation (The Commission :, 1980), by S. F. Masri, S. J. Stott, University of Southern California. Department of Civil Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Magnetic gear for torque transfer to an enclosed system (War Department, Corps of Engineers, Office of the District Engineer, Manhattan District, 1946), by T. A. Abbott, James K. Pickard, U.S. Atomic Energy Commission, and Kellex Corporation (page images at HathiTrust)
• A combination strainer and blocking valve for liquid metal systems (Atomics International, 1960), by F. S. Nayor, J. S. McDonald, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A siphon break as a blocking valve (Atomics International, 1959), by J. McDonald, W. Marten, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)

• Liquid metal fuel reactor experiment : a gas-shielded consumable-electrode arc welding process for butt welding croloy 2-1/4 piping (Office of Technical Services., 1959), by R. M. Hargrove, U.S. Atomic Energy Commission, and Babcock & Wilcox Company (page images at HathiTrust)
• Ultrasonic and metallurgical examination of a cracked type 304 stainless steel BWR pipe weldment (Argonne, Illinois : Argonne National Laboratory, 1984., 1984), by J. Y. Park, D. S. Kupperman, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and Argonne National Laboratory. Materials Science and Technology Division (page images at HathiTrust)

• Effects of postulated event devices on normal operation of piping systems in nuclear power plants (Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission.:, 1981), by D. F. Landers, K. D. Desai, R. D. Hookway, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering, and Teledyne Engineering Services (page images at HathiTrust)

More items available under broader and related terms at left.