Reactor components - Open Access .click

Thermal Science of Advanced Steam Generators/Heat Exchangers, 1996
Abstract Several experiments have recorded loop stratification at a recent test performed at the Rig of Safety Assessment (ROSA) project at the Japanese Atomic Energy Research Institute’s Large Scale Test. This facilty (LSTF) is used for for the advanced nuclear reactor AP600 simulation.
J. A. Randorf, Y. A. Hassan
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Component vibration of VVER-reactors — diagnostics and modelling

Progress in Nuclear Energy, 1995
Abstract Flow induced vibrations of reactor pressure vessel (RPV) internals (control element and core barrel motions) at VVER-440 reactors have lead to the development of dedicated methods for on-line monitoring. These methods need a certain developed stage of the faults to be detected. To achieve a real sensitive early detection of mechanical faults
Altstadt, E. +4 more
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A review of flow-induced vibrations in reactors and reactor components

Nuclear Engineering and Design, 1983
Abstract This paper presents a review of the state of the art of two classes of vibration problems encountered in reactors and reactor peripherals: namely, vibration of cylindrical structures induced by cross flow and by axial flow. A historical perspective is given first, in which the milestone contributions that have advanced the state of the art ...
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