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Flow-induced vibration handbook for nuclear and process equipment First edition (Wiley-ASME Press series)

Flow-induced vibration handbook for nuclear and process equipment First edition (Wiley-ASME Press series)
紙図書
[edited by] Michel J. Pettigrew, Colette E. Taylor, Nigel J. FisherJohn Wiley & Sons, Inc.[2022]<MC75-D10>
国立国会図書館

Final report on advanced nondestructive evaluation for steam generator tubing for the Second International Steam Generator Tube Integrity Program [microform] / prepared by S. Bakhtiari ... [et al.] NUREG/CR-6814 ANL-03/4

Final report on advanced nondestructive evaluation for steam generator tubing for the Second International Steam Generator Tube Integrity Program [microform] / prepared by S. Bakhtiari ... [et al.] NUREG/CR-6814 ANL-03/4
マイクロ図書
2003<YCA-Y 3.N 88:25/6814>
国立国会図書館
  • 件名Nuclear power plants -- Piping Nondestructive testing

Second U.S. Nuclear Regulatory Commission international steam generator tube integrity research program [microform] : final project summary report / prepared by S. Bakhtiari ... [et al.] NUREG/CR-6804 ANL-02/28

Second U.S. Nuclear Regulatory Commission international steam generator tube integrity research program [microform] : final project summary report / prepared by S. Bakhtiari ... [et al.] NUREG/CR-6804 ANL-02/28
マイクロ図書
2003<YCA-Y 3.N 88:25/6804>
国立国会図書館
  • 件名Steam-boiler inspection Nuclear power plants -- Piping

MOV stem lubricant aging research [microform] / prepared by K.G. DeWall, J.C. Watkins

MOV stem lubricant aging research [microform] / prepared by K.G. DeWall, J.C. Watkins
マイクロ図書
2003<YCA-Y 3.N 88:25/6806>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Valves Lubrication and lub...

Development of technical basis for leak-before-break evaluation procedures [microform] / prepared by P.M. Scott, R.J. Olson, G.M. Wilkowski

Development of technical basis for leak-before-break evaluation procedures [microform] / prepared by P.M. Scott, R.J. Olson, G.M. Wilkowski
マイクロ図書
2002<YCA-Y 3.N 88:25/6765>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- United States -- Evaluatio...

Fracture toughness and crack growth rates of irradiated austenitic stainless steels [microform] / prepared by O.K. Chopra, E.E. Gruber, W.J. Shack NUREG/CR-6826 ANL-03/22

Fracture toughness and crack growth rates of irradiated austenitic stainless steels [microform] / prepared by O.K. Chopra, E.E. Gruber, W.J. Shack NUREG/CR-6826 ANL-03/22
マイクロ図書
2003<YCA-Y 3.N 88:25/6826>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Deterioration Austenitic s...

Heat pipe applications in fission driven nuclear power plants

Heat pipe applications in fission driven nuclear power plants
紙図書
Bahman ZohuriSpringerc2019
全国の図書館
  • 件名Heat pipes Nuclear power plants -- Piping
  • 件名（識別子）Heat pipes Nuclear power plants -- Piping

In-tube steam condensation in the presence of air [microform] / prepared by A. Tanrikut, O. Yesin (International agreement report ; NUREG/IA-0184)

In-tube steam condensation in the presence of air [microform] / prepared by A. Tanrikut, O. Yesin (International agreement report ; NUREG/IA-0184)
マイクロ図書
2000<YCA-Y 3.N 88:53/0184>
国立国会図書館
  • 件名Condensation Steam -- Thermal properties Nuclear power plants -- Piping

Results of pressure locking and thermal binding tests of gate valves [microform] / prepared by K.G. DeWall ... [et al.]

Results of pressure locking and thermal binding tests of gate valves [microform] / prepared by K.G. DeWall ... [et al.]
マイクロ図書
1998<YCA-Y 3.N 88:25/6611>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Valves -- Testing Nuclear power plants -- Piping -- Valves -- Reliability

A study of air-operated valves in U.S. nuclear power plants [microform] / prepared by O. Rothberg ... [et al.]

A study of air-operated valves in U.S. nuclear power plants [microform] / prepared by O. Rothberg ... [et al.]
マイクロ図書
2000<YCA-Y 3.N 88:25/6654>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Valves -- United States Re...

A comparison of three round robin studies on ISI reliability of wrought stainless steel piping [microform] / prepared by P.G. Heasler, S.R. Doctor

A comparison of three round robin studies on ISI reliability of wrought stainless steel piping [microform] / prepared by P.G. Heasler, S.R. Doctor
マイクロ図書
2003<YCA-Y 3.N 88:25/6795>
国立国会図書館
  • 件名...als -- Testing Nuclear power plants -- Piping -- Testing

Technical elements of risk-informed inservice inspection programs for piping [microform] : draft report

Technical elements of risk-informed inservice inspection programs for piping [microform] : draft report
マイクロ図書
1999<YCA-Y 3.N 88:10/1661>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Inspection -- United State...

Proceedings of the Sixth NRC/ASME Symposium on Valve and Pump Testing [microform] : held at Hyatt Regency Hotel, Washington, DC, July 17-20, 2000 / edited by T.G. Scarbrough, M. Kotzalas ; jointly sponsored by Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission [and] Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers (NUREG/CP ; 0152)

Proceedings of the Sixth NRC/ASME Symposium on Valve and Pump Testing [microform] : held at Hyatt Regency Hotel, Washington, DC, July 17-20, 2000 / edited by T.G. Scarbrough, M. Kotzalas ; jointly sponsored by Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission [and] Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers (NUREG/CP ; 0152)
マイクロ図書
2000<YCA-Y 3.N 88:27/0152/V.3>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Valves -- Congresses Pumpi...

A methodology for evaluation of inservice test intervals for pumps and motor-operated valves [microform] / prepared by K.L. McElhaney ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

A methodology for evaluation of inservice test intervals for pumps and motor-operated valves [microform] / prepared by K.L. McElhaney ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
1999<YCA-Y 3.N 88:25/6578>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Valves -- Testing Pumping ...

Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes [microform] / prepared by S. Majumdar, K. Kasza, J. Franklin ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Pressure and leak-rate tests and models for predicting failure of flawed steam generator tubes [microform] / prepared by S. Majumdar, K. Kasza, J. Franklin ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
2000<YCA-Y 3.N 88:25/6664>
国立国会図書館
  • 件名Steam-boilers -- Testing Pressure vessels -- Testing Nuclear power plants -- Piping -- Cracking

The role of time-dependent deformation in intergranular crack initiation of alloy 600 steam generator tubing material [microform] / prepared by G.S. Was, K. Lian (NUREG/GR ; 0016)

The role of time-dependent deformation in intergranular crack initiation of alloy 600 steam generator tubing material [microform] / prepared by G.S. Was, K. Lian (NUREG/GR ; 0016)
マイクロ図書
1998<YCA-Y 3.N 88:58/0016>
国立国会図書館
  • 件名Steam-boilers -- Materials -- Stress corrosion Nuclear power plants -- Piping

Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work [microform] / prepared by E.C. Rodabaugh, R.C. Gwaltney, S.E. Moore

Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work [microform] / prepared by E.C. Rodabaugh, R.C. Gwaltney, S.E. Moore
マイクロ図書
1993<YCA-Y 3.N 88:25/5358>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Stress corrosion Nuclear power plants -- Piping -- Fatigue

Proceedings of the Fifth NRC/ASME Symposium on Valve and Pump Testing [microform] : held at Hyatt Regency Hotel, Washington, DC, July 20-23, 1998 / edited by Joseph Colaccino, Thomas G. Scarbrough ; sponsored by Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission [and] Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers (NUREG/CP ; 0152)

Proceedings of the Fifth NRC/ASME Symposium on Valve and Pump Testing [microform] : held at Hyatt Regency Hotel, Washington, DC, July 20-23, 1998 / edited by Joseph Colaccino, Thomas G. Scarbrough ; sponsored by Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission [and] Board on Nuclear Codes and Standards of the American Society of Mechanical Engineers (NUREG/CP ; 0152)
マイクロ図書
1998<YCA-Y 3.N 88:27/0152/V.2>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- Valves -- Congresses Pumpi...

Fatigue analysis of components for 60-year plant life [microform] / prepared by M.A. Khaleel ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Fatigue analysis of components for 60-year plant life [microform] / prepared by M.A. Khaleel ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
2000<YCA-Y 3.N 88:25/6674>
国立国会図書館
  • 件名...als -- Fatigue Nuclear power plants -- Piping -- Fatigue

Steam generator tube integrity program [microform] / prepared by D.R. Diercks ... [et al.]

Steam generator tube integrity program [microform] / prepared by D.R. Diercks ... [et al.]
マイクロ図書
1998<YCA-Y 3.N 88:25/6511/V.3>
国立国会図書館
  • 件名Nuclear power plants -- Piping -- United States Steam-pipes ...