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Maintenance supply chain for nuclear power plants : information technology support for human resources management
Andrej Androjna, Robert Bizjak, Bojan Rosi, 2009, original scientific article

Abstract: The paper is looking at a case on IT support of HR management in a maintenance supply chain for nuclear power plants and analyzing a specific solution developed by NUMIP Ltd. The database NOS Data developed by NUMIP Ltd.has proved to be an efficient tool for the intended purpose and size of the current application. Yet there is a clear potential for improvement of the tool in the future, mainly related to direct electronic data exchange with customers and subcontractors, as well as to implementation of requirements of nuclear plants from different markets. The case study provides a description of a relatively complex requirement structure that applies to outsourced personnel working in maintenance activities in a nuclear power plant. The area is rather poorly covered in literature, hence the paper may be of interest to practitioners and students, as well as researchers.
Keywords: supply chain, maintenance, nuclear power plant, information technology, human resources
Published: 05.06.2012; Views: 1170; Downloads: 33
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Simulation of flow conditions in nuclear power plant reactor pressure vessel lower plenum experimental facility
Blaž Kamenik, 2019, master's thesis

Abstract: The flow conditions during the experiment LIVE2D on reactor core melt behaviour in the lower plenum of a reactor pressure vessel, performed at the Karlsruhe Institute of Technology (Germany), were simulated with a Computational Fluid Dynamics computer code. In this hypothetical severe accident scenario in a pressurized water reactor nuclear power plant, the melt is divided into an oxidic layer and a metallic layer on top of it, and the oxidic layer is volumetrically heated due to decay heat. In the experiment, oil and salt were used as simulant materials for metallic and oxidic melt, respectively. The main goal of performed simulations was to investigate the so-called “focusing effect”, where a thin layer of the reactor vessel steel wall is exposed to high heat flux. Due to the length of experiment, which exceeds 100 hours, only intervals of the melt behaviour were simulated. Four cases were simulated. The first case investigated different boundary conditions for the oil layer behaviour for layer thickness 35 mm. The second case investigated the same conditions with added modelling of the reactor vessel steel wall and salt crust from the lower layer. The third case used similar modelling as the second case to investigate the oil layer behaviour for layer thickness 75 mm. The fourth case investigated both salt and oil layers for oil layer thickness 75 mm. Different analytical and numerical calculations were performed to determine heat losses from simulant liquids to the surroundings, which played an important part in the experiment.
Keywords: nuclear power plant, severe accident, reactor core melt, lower plenum, heat flux focusing effect
Published: 17.09.2019; Views: 21; Downloads: 9
.pdf Full text (6,83 MB)

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