1-20 of 39
Keywords: fission reactor materials
Close
Sort by
Journal Articles
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. February 2012, 134(1): 014501.
Published Online: December 20, 2011
... 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 approaches to plant-life management as licensees seek...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2011, 133(2): 021403.
Published Online: March 14, 2011
... in Korea. fracture toughness leak-before-break narrow gap weld nuclear piping tensile strength welding residual stress deformation finite element analysis fission reactor materials fracture toughness testing internal stresses nuclear power stations pipes shrinkage stainless steel...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2009, 131(4): 041407.
Published Online: July 1, 2009
... initiation than the other tube, which may be attributed to the differences in their microstructure and texture. There is a reasonable agreement between the test results and the predictions from the EPZ model. 07 11 2007 01 09 2008 01 07 2009 fission reactor materials fission reactor...
Journal Articles
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. August 2009, 131(4): 044002.
Published Online: May 26, 2009
... for the development of constitutive equations. They are also used for developing material specific multiaxial creep-rupture strength theories used in the code. 13 08 2007 24 02 2009 26 05 2009 alloys cracks creep fatigue fission reactor materials heat exchangers Alloys 617...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2009, 131(1): 011404.
Published Online: November 26, 2008
.... , 2007 , “ Development of a Stress Corrosion Crack Test Methodology Using Tube-Shaped Specimen ,” J. Test. Eval. 0090-3973 10.1520/JTE100628 , 35 ( 3 ), pp. 254 – 258 . cracks elasticity finite element analysis fission reactor materials fission reactor theory nuclear power stations...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2007, 129(3): 488–506.
Published Online: November 28, 2006
... LWR materials and conditions exhibits similar dependencies and occurs by a common mechanism ( 2 5 6 7 8 9 ), with the crack tip always deaerated and at low potential. stainless steel fission reactor materials nickel alloys stress corrosion cracking internal stresses crack-edge stress...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 2007, 129(2): 262–271.
Published Online: September 3, 2006
... of the weldment to the measured results shows that the numerical results reproduce the measured results well. 14 09 2005 03 09 2006 welds computational fluid dynamics nuclear engineering computing fission reactor materials weld thermal analysis steady state Eulerian moving...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2007, 129(3): 482–487.
Published Online: August 21, 2006
... fission reactor materials heat transfer mechanical testing welds fission reactor cooling The author of this paper and others have long been advocates of hybrid expanding the tubes into tubesheets of tubular heat transfer equipment whether the joining is by expanding only or by welding followed...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2007, 129(1): 169–174.
Published Online: July 11, 2006
... discharge machining fission reactor materials eddy current examination fatigue crack Inconel weld reconstruction Various cracking phenomena have been reported in nuclear power plants in recent years. One major cracking occurred in nickel alloy welded joints (Inconel welds), such as nozzle...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2007, 129(3): 400–410.
Published Online: June 7, 2006
... fatigue crazing stainless steel crack arrest shot peening weld residual stress fission reactor cooling fission reactor materials crazing fatigue cracks thermal stress cracking internal stresses shot peening welds compressibility fatigue testing work hardening stainless steel...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2007, 129(1): 186–194.
Published Online: June 1, 2006
... 0.3 0.4 1 ∕ 4 * N f 3 83 0.03 0.6 0.4 1 ∕ 4 * N f 1 0 — 237 0.52 18 01 2006 01 06 2006 fatigue fission reactor materials austenitic stainless steel alloy steel carbon steel fission reactor safety In the last...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2007, 129(1): 28–37.
Published Online: March 13, 2006
... as a function of number of load cycles and should be applied to the monotonic critical load. 26 08 2005 13 03 2006 fission reactor design fission reactor materials fracture nuclear power stations cracks fission reactor safety fracture toughness cyclic tearing reverse cyclic...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2006, 128(1): 64–70.
Published Online: October 19, 2005
... 19 10 2005 nuclear facility regulation fatigue fracture mechanics pressure vessels fission reactor design fission reactor materials flaw detection fission reactor monitoring ageing elastoplasticity The present series of papers was prepared to introduce the activities...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2006, 128(1): 57–63.
Published Online: October 19, 2005
... with two charts (see Fig. 5 ). nuclear facility regulation nuclear power stations fatigue fracture toughness elastoplasticity thermal stress cracking finite element analysis pressure vessels fission reactor design fission reactor materials Significant changes have recently been...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 2005, 127(4): 525–529.
Published Online: June 3, 2005
.... BIS , 2000 , “ IS: 456, Indian Standard Code of Practice for Plain and Reinforced Concrete ,” Fourth Revision, Bureau of Indian Standards, New Delhi, India. ducts fission reactor design fission reactor materials fission reactor safety seismology earthquakes stress analysis design...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 2005, 127(2): 119–122.
Published Online: May 27, 2005
...; revision received September 22, 2004. Review conducted by: K. K. Yoon. 02 September 2003 22 September 2004 27 05 2005 thermal stresses stress analysis solar radiation fission research reactors finite element analysis fission reactor theory fission reactor materials fission...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 2005, 127(2): 123–128.
Published Online: May 27, 2005
.... Review conducted by: K. K. Yoon. 15 September 2003 22 September 2004 27 05 2005 finite element analysis failure (mechanical) cracks fission reactor materials fission reactor theory plastic deformation nuclear reactor maintenance Steam Generator Tube Plastic Collapse...
Journal Articles
Journal Articles
Publisher: ASME
Article Type: Article
J. Pressure Vessel Technol. February 2005, 127(1): 55–60.
Published Online: March 15, 2005
.... Associate Editor: M. D. Rana. 26 February 2004 30 August 2004 15 03 2005 pressure vessels nuclear engineering computing fission reactor design fission reactor materials fission reactor theory fires fission reactor safety fracture steel tanks (containers) Pressure...
Journal Articles
Publisher: ASME
Article Type: Article
J. Pressure Vessel Technol. February 2005, 127(1): 76–83.
Published Online: March 15, 2005
...; revision received July 8, 2004. Review conducted by: R. J. Scavuzzo. 27 August 2003 08 July 2004 15 03 2005 stress analysis fission reactor materials pipes creep failure analysis bending geometry pressure vessels Combined Loading Local Wall Thinning Failure Stress...