Wagner R.,Karlsruhe Institute of Technology |
Wagner R.,Kraftanlagen Heidelberg GmbH |
Demange D.,Karlsruhe Institute of Technology |
Fanghanel E.,Karlsruhe Institute of Technology |
And 3 more authors.
Fusion Science and Technology | Year: 2015
The PETRA facility is the first installation in which experiments with tritium were carried out at the Tritium Laboratory Karlsruhe. After completion of two main experimental programs, the decommissioning of PETRA was initiated with the aim to reuse the glove box and its main still valuable components. A decommissioning plan was engaged to: i) identify the source of tritium release in the glove box, ii) clarify the status of the main components, iii) assess residual tritium inventories, and iv) detritiate the components to be disposed of as waste. Several analytical techniques - calorimetry on small solid samples, wipe test followed by liquid scintillation counting for surface contamination assessment, gas chromatography on gaseous samples - were deployed and cross-checked to assess the remaining tritium inventories and initiate the decommissioning process. The methodology and the main outcomes of the numerous different tritium measurements are presented and discussed. © 2015, American Nuclear Society. All rights reserved.
Spagnuolo G.A.,Kraftanlagen Heidelberg Gmbh |
Dell'Orco G.,ITER Organization |
Di Maio P.A.,University of Palermo |
Mazzei M.,Kraftanlagen Heidelberg Gmbh
Fusion Engineering and Design | Year: 2015
The Tokamak Cooling Water System of nuclear facility has the function to remove heat from plasma facing components maintaining coolant temperatures, pressures and flow rates as required and, depending on thermal-hydraulic requirements, its systems are defined as High Energy Piping (HEP) because they contain fluids, such as water or steam, at a pressure greater than or equal to 2.0 MPa and/or at a temperature greater than or equal to 100 °C, or even gas at pressure above the atmospheric one. The French standards contemplate the need to consider the whipping effect on HEP design. This effect happens when, after a double ended guillotine break, the reaction force could create a displacement of the piping which might affect adjacent components. A research campaign has been performed, in cooperation by ITER Organization and University of Palermo, to outline the procedure to check whether whipping effect might occur and assess its potential damage effects so to allow their mitigation. This procedure is based on the guidelines issued by U.S. Nuclear Regulatory Commission. The proposed procedure has been applied to the analysis of the whipping effect of divertor primary heat transfer system HEP, using a theoretical-computational approach based on the finite element method. © 2015 Elsevier B.V. All rights reserved.