... could have different interpretations depending 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...

... 2008 17 04 2009 fission reactors fracture toughness inspection standards steel In the 1960s and 1970s the surveillance programs for currently operating commercial nuclear reactors were established. The then-current state of knowledge of fracture mechanics required the testing...

... with the classical coupled method in terms of eigenfrequencies, eigenmodes, and effective modal masses. 17 08 2007 08 02 2008 11 02 2009 boilers eigenvalues and eigenfunctions finite element analysis fission reactor safety fission reactors heat exchangers modal analysis Dynamic...

... on Dislocation Density Evolution ,” High Temperature Constitutive Modelling-Theory and Application , American Society of Mechanical Engineers , New York , MD-Vol. 26 , pp. 65 – 83 . 05 10 2006 25 04 2007 30 12 2008 ageing alloys cracks creep fracture fatigue fission reactors...

... fission reactor cooling fission reactors nozzles pressure vessels thermal stresses transient response Thermal sleeves are installed in the skirt position of SI nozzle to protect the nozzle part of SI line against the potential thermal fatigue, which can be caused by the direct contact of cold...

... mechanism. 25 04 2004 08 08 2005 stress corrosion cracking nickel alloys deformation oxidation yield strength fission reactors stress corrosion cracking crack growth rate nickel-base alloy alloy 600 light water reactor pressurized water reactor boiling water reactor...

... ENGINEERS . Manuscript received by the PVP Division, December 4, 2000; revised manuscript received December 18, 2001. Editor: S. Y. Zamrik. 23 July 2000 04 December 2000 18 December 2001 01 05 2002 thermal analysis fission reactors stagnation flow heavy water...

...%. Based on these results and authors’ earlier work, a modification to ASME Code formulas is proposed for calculation of more realistic values of the stress indices for bends up to 180 deg. pipe flow stress analysis stress control stress measurement pressure vessels fission reactors fission...

... of the RPV, it is essential to model creep behavior and rupture properly. creep creep testing viscoplasticity deformation pressure vessels fission reactors fission reactor core control melting 23 July 2000 27 October 2000 05 February 2001 Contributed by the Pressure...

... cracks stainless steel boiling fission reactors fatigue water About thirty years have passed since the start of operation of the first-generation Japanese light-water reactors, and possible degradation of any structural component cannot necessarily be denied. Current Japanese design rule...

... of the procedure. irradiation induced creep fission reactors performance evaluation fission reactor design pressure vessels stainless steel neutron flux neutron effects radiation effects mechanical properties creep testing chromium alloys molybdenum alloys 01 August 1999 18...

... received by the PVP Division, October 13, 1998; revised manuscript received January 27, 2000. Associate Technical Editor: R. C. Gwaltney. 23 July 1995 13 October 1998 27 January 2000 design engineering fission reactor design deformation thermal stresses temperature...

... by the PVP Division, June 14, 1999; revised manuscript received January 27, 2000. Associate Technical Editor: G. C. Slagis. 14 June 1999 27 January 2000 dynamics nuclear power fission reactors wear modelling vibrations pressure vessels Dynamic response analysis...

... pressure vessels elasticity cooling fission reactors Figure 2 shows the system under consideration. It consists of a flexible plate weir and adjoining fluid plenums. The fluid is supplied from the bottom of the upstream plenum and restituted from the bottom of the downstream plenum...