This publication contains papers presented at an IAEA technical meeting, held in Cadarache, France in November 2004, to discuss a range of topics relating to technical developments in pressurised water reactors (PWR) and water cooled, water moderated, electricity generating reactors (WWER), including the impact of hydraulic loadings on fuel assembly (FA) performance; FA bow and control rod (CR) drop kinetics; vibrations and rod-to-grid wear and fretting; evaluation and modelling of and accident conditions, mainly from seismic causes. HEWLETT PACKARD, Usera#39;s Manual of HPVEE 5.0 ( 1 999). ... Evaluation of Flow-induced Vibration for Fixed Type Guide Rods of Shroud Head and Steam Dryer in ABWR, ICON El ...  I.K. MADNI, L.G. STEPHENS, and D.M. TURNER, Development of Correlations for Pressure Loss/Drop Coefficients Obtained fromanbsp;...
|Title||:||Structural Behaviour of Fuel Assemblies for Water Cooled Reactors|
|Author||:||International Atomic Energy Agency|