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Keywords: nuclear power stations
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Journal Articles
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. February 2012, 134(1): 014501.
Published Online: December 20, 2011
... 03 2011 01 09 2011 20 12 2011 20 12 2011 fission reactor materials nondestructive testing nuclear power stations There is a growing global interest in the longer term operation (LTO) of the existing fleet of nuclear power plants (NPPs). This requires new and improved...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2012, 134(1): 011201.
Published Online: December 1, 2011
... parameter method condition monitoring failure analysis fatigue Green's function methods materials properties nuclear power stations remaining life assessment 02 03 2011 09 05 2011 01 12 2011 01 12 2011 α 2 = 0 W/m 2 /°C T 0 = 0 °C Time histories of fluid...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. December 2011, 133(6): 061203.
Published Online: October 19, 2011
... automatic optical inspection crack detection design engineering finite element analysis gradient methods nuclear power stations thermal stress cracking thickness measurement walls thermal fatigue thermal stress crack propagation crack network crack arrest mixing tee Some...
Journal Articles
Publisher: ASME
Article Type: Errata
J. Pressure Vessel Technol. October 2011, 133(5): 057001.
Published Online: August 23, 2011
...R. I. Jetter; T.-L. Sham; R. W. Swindeman 23 08 2011 23 08 2011 creep nuclear power stations pressure vessels We are grateful to Dr. Richard N. Wright of the Idaho National Laboratory for the support of this work. We thank Mr. Masanori Ando of the Japan Atomic Energy...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. October 2011, 133(5): 051208.
Published Online: July 14, 2011
... finite element analysis heat exchangers hydrogen production nuclear power stations process heat exchanger creep-fatigue damage Alloy 617 draft code case for Alloy 617 high temperature design code The generation of hydrogen using nuclear energy has become a viable means of producing...
Journal Articles
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. August 2011, 133(4): 044001.
Published Online: May 11, 2011
... economy. 06 05 2010 14 07 2010 11 05 2011 11 05 2011 economics energy resources fission fission reactor coolants nuclear fusion nuclear power stations recycling uranium This paper addresses two major questions: What are the challenges to nuclear fission...
Journal Articles
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. June 2011, 133(3): 034001.
Published Online: April 6, 2011
... 2010 06 04 2011 06 04 2011 decision making fission reactor safety inspection maintenance engineering nuclear power stations occupational safety production management Contri , P. , 2006 , “ Optimisation of Maintenance Programs in View of Long Term Operation...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2011, 133(2): 021403.
Published Online: March 14, 2011
... strength welding residual stress deformation finite element analysis fission reactor materials fracture toughness testing internal stresses nuclear power stations pipes shrinkage stainless steel tensile testing welding welds 07 01 2010 06 07 2010 14 03 2011 14 03...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2011, 133(2): 021103.
Published Online: February 14, 2011
... on what failure modes are considered and the associated criteria for avoiding the effects of creep. boilers creep failure (mechanical) fission reactors nuclear power stations pressure vessels softening stress analysis 11 04 2009 11 05 2010 14 02 2011 14 02 2011...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2011, 133(2): 021102.
Published Online: January 31, 2011
... Class 2/3 nuclear piping is limited to 800F, and therefore, creep is not a concern. creep design engineering fatigue nuclear power stations pipes thermal expansion thermal stresses 13 07 2007 16 12 2009 31 01 2011 31 01 2011 2011 American Society...
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. February 2011, 133(1): 014505.
Published Online: January 21, 2011
... collaboration knowledge management nuclear power stations production engineering computing 15 02 2010 20 07 2010 21 01 2011 21 01 2011 2011 American Society of Mechanical Engineers ...
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. February 2011, 133(1): 014501.
Published Online: January 20, 2011
... 20 01 2011 equipment selection materials properties nuclear power stations pipes The material selection methodology used in Czech Nuclear Power Plant (NPP) is summarized in the Standard Technical Documentation (STD) of the Association of Mechanical Engineers (AME), Sec. II...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2011, 133(1): 011206.
Published Online: December 23, 2010
... 12 2010 23 12 2010 buckling nuclear power stations pipes steam generators integrated primary system nuclear reactors collapse thick tubes external pressure imperfections sensitivity The assessment of load bearing capacity of shells can be considered an issue...
Journal Articles
Randy K. Nanstad, B. Richard Bass, John G. Merkle, Claud E. Pugh, Thomas M. Rosseel, Mikhail A. Sokolov
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. December 2010, 132(6): 064001.
Published Online: October 14, 2010
... 10 2010 14 10 2010 fatigue cracks fracture toughness neutron effects nondestructive testing nuclear power stations plates (structures) steel thermal shock heavy-section steel drop-weight NDT thermal shock pressurized thermal shock reactor pressure vessel fracture...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. December 2010, 132(6): 061204.
Published Online: October 14, 2010
... numerical examples are provided to show its effectiveness. crack detection inspection nuclear power stations pipes stainless steel stress analysis stress corrosion cracking multiple flaws collapse bending stress failure membrane stress limit load criterion fitness for service...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. October 2010, 132(5): 051501.
Published Online: August 25, 2010
... detection nuclear power stations polyethylene insulation ultrasonic arrays ultrasonic materials testing Metal is the predominantly used material for piping and other pressure retaining components used in the nuclear industry, which are designed to the ASME Boiler and Pressure Vessel Code. Even...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. June 2010, 132(3): 031101.
Published Online: May 4, 2010
... evaluation, according to the ASME-NH and RCC-MR for the cross vessel of Mod.9Cr-1Mo steel, has been conducted and their results were compared. 14 04 2009 06 11 2009 04 05 2010 04 05 2010 code standards creep fracture ducts fatigue nuclear power stations steel structural...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2010, 132(2): 021101.
Published Online: March 31, 2010
... for the variables under consideration are presented and the partial safety factors are moreover illustrated for different values of the target reliability index. 15 11 2009 28 12 2009 31 03 2010 31 03 2010 design engineering nuclear power stations pipes pressure vessels reliability...
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. April 2010, 132(2): 024501.
Published Online: January 29, 2010
... of degradation have caused shutdowns, and leaks have become a maintenance issue. This brief will present a description of erosive damage mechanisms found in nuclear power plants. 30 11 2007 21 08 2009 29 01 2010 29 01 2010 corrosion environmental degradation erosion nuclear power...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2010, 132(2): 021203.
Published Online: January 26, 2010
... Koiter’s theorem. Furthermore, the results are compared with cycle-by-cycle method based on nonlinear material properties. 03 07 2008 28 09 2009 26 01 2010 26 01 2010 elastoplasticity finite element analysis nuclear power stations elastic-plastic cyclic load shakedown...
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