... failure analysis fatigue testing fission reactor design fission reactor safety fracture mechanics inspection nuclear reactor maintenance For the improvement of in-service inspection planning of nuclear plants, risk-based technologies have been implemented to a number of light water reactors...

... 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...

... ,” in Pressure Vessel and Piping: Design and Analysis, A Decade of Progress, Volume 1, Analysis , ASME , New York , pp. 209 – 226 [reprint of ASME Paper No. 68-PVP-3, 1968 ]. 26 08 2005 24 10 2005 nuclear engineering fission reactor design thermal stresses ductility design...

...Heki Shibata 20 10 2005 24 10 2005 nuclear power stations earthquakes nuclear reactor maintenance failure analysis fission reactor design fission reactor safety seismology nuclear facility regulation This papers deals with the importance of input ground motions...

... 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...

... 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...

.... 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...

... Interaction in a High Velocity Vapor Jet Condensing in a Coaxial Water Flow ,” ASME J. Heat Transfer , 3 , pp. 226 – 230 . fission reactor cooling heat transfer flow computational fluid dynamics nuclear engineering computing fission reactor design condensation fission reactor kinetics...

... Division December 4, 2003; revision received September 8, 2004. Review conducted: W. L. Cheng. 04 December 2003 08 September 2004 15 03 2005 nuclear power stations fission reactor cooling fission reactor theory fission reactor design pipes valves nuclear engineering...

.... 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...

... vessels fission reactor design carbon fibre reinforced composites steel stress effects The basis tube is illustrated in Fig. 1 . It has a bore radius of 50 mm and an outer radius of 100 mm. The elastic hoop and radial stresses within such a tube, when pressurized to 500 MPa, are shown in Fig...

... nuclear reactor maintenance testing fission reactor design nuclear power stations risk analysis pressure vessels optimisation Risk-Based Inservice Testing Multiobjective Optimization Surveillance Test Interval Unavailability Maintenance Costs Probabilistic Risk Analysis...

.... corrosion resistance pressure vessels stainless steel scanning electron microscopy Auger electron spectra X-ray diffraction electrolysis metallography failure analysis fission reactor design Hydrogen (oxygen) generating system by water electrolysis is widely used to supply hydrogen...

... plasticity steel geometry boilers fission reactor design This paper examines the design criterion for fatigue analysis on plastic basis that is specified in Sections III and VIII of the ASME B&PV Code 1 (henceforth the Code). (These rules provide an alternative to fatigue analysis...

... fission reactor design two-phase flow nuclear engineering computing damping vibrations heat exchangers reviews 02 July 2002 05 May 2004 01 12 2004 Contributed by the Pressure Vessels and Piping Division for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY...

...Gerry Slagis 26 02 2004 pressure vessels fission reactor design fission reactor safety earthquakes seismology fission reactor materials nuclear engineering computing This special issue of the ASME Journal of Pressure Vessel Technology is focused on various technical...

... and other members of the subcommittee on the seismic design of piping systems. nuclear power stations seismology earthquakes fission reactor design fission reactor materials fission reactor safety pressure vessels One of the authors (Shibata) primarily intended to prepare a paper titled...

... reactor design nuclear reactor maintenance nuclear engineering computing soil 3 Variation of shear modulus with shear strain for cohesionless soil (after Seed and Idriss 3 and Seed et al. 4 ) SAP4 frequency analysis on SASSI model of reactor core model include reactor core...

...; revision received June 27, 2003. Associate Editor: S. Y. Zamrik. 23 June 2003 27 June 2003 04 11 2003 fission reactor cooling steel fatigue cracks stress-strain relations fission reactor safety fission reactor design fission reactor materials The authors...

... materials fission reactor safety fission reactor design fission reactor cooling 22 April 2003 02 June 2003 04 11 2003 Contributed by the Pressure Vessels and Piping Division for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY . Manuscript received by the PVP Division...