Qucosa – Hemholtz-Zentrum Dresden-Rossendorf
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Nutzung einer zukünftigen Synchrotronstrahlungsquelle, Arbeitstreffen am 15. und 16. Dezember 1992 in Dresden, Sammlung der Beiträge
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Acoustic Leak Detection at Complicated Geometrical Structures Using Fuzzy Logic and Neural Networks
Get PDFMethods of acoustic leak monitoring are of great practical interest for the safety of pressure vessels and pipe lines not only at the primary circuit of nuclear power plants. In this report some aspects of acoustic leak localization at complicated three-dimensional topologies for the case of leakage monitoring at the reactor vessel head of a VVER-440 are discussed. An acoustic method based on pattern recognition is being developed. During the learning phase, the localization classifier is trained with sound patterns that are generated with simulated leaks at all locations endangered by leak. After training unknown leak positions can be recognized through comparison with the training patterns. The sound patterns of the simulated leaks are simultaneously detected with an AE-sensor array and with high frequency microphones measuring structureborne sound and airborne noise, respectively. The initial results show the used classifiers principally to be capable of detecting and locating leaks, but they also show that further investigations are necessary to develop a reliable method
The Code DYN3D/M2 for the Calculation of Reactivity Initiated Transients in Light Water Reactors with Hexagonal Fuel Elements -Code Manual and Input Data Description-
Get PDFThe code DYN3D/M2 is used for investigations of reactivity transients in cores of thermal power reactors with hexagonal fuel elements. The 3-dimensional neutron kinetics model HEXDYN3D of the code is based on a nodal expansion method for solving the two-group neutron diffusion equation. The thermo-hydraulic part FLOCAL consists of a two-phase flow model describing coolant behaviour and a fuel rod model. The fuel elements are simulated by separate coolant channels. Additional, some hot channels with power peaking factors belonging to chosen fuel elements can be considered. Several safety parameters as temperatures, DNBR and fuel enthalpy are evaluated. Macroscopic cross sections depending from the thermo-hydraulic parameters and boron concentration are input data of the code. The stationary state and transient behaviour can be analyzed. The arrangement of input data are descibed for using the different option of the code
