RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE

This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. The dry spent fuel storage sub-channel code COBRA-SFS has been used in order to calculate the temperature field. In this code, the new model of residual heat removal was created for the SKODA 1000/19...

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Main Author: Daniel Vlček
Format: Article
Language:English
Published: Czech Technical University in Prague 2018-12-01
Series:Acta Polytechnica CTU Proceedings
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Online Access:https://ojs.cvut.cz/ojs/index.php/APP/article/view/5231
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author Daniel Vlček
author_facet Daniel Vlček
author_sort Daniel Vlček
collection DOAJ
description This project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. The dry spent fuel storage sub-channel code COBRA-SFS has been used in order to calculate the temperature field. In this code, the new model of residual heat removal was created for the SKODA 1000/19 cask where the spent nuclear fuel TVSA-T type from NPP Temelin will be stored. The object of calculations was to obtain the inside temperatures under maximum loads. After that, the results were compared to the requirements of the local regulatory body. Because of the absence of experimental data, the validation of the created computational models could not be accomplished. However, according to the verification scheme of the COBRA-SFS authors, the verification of the new models was implemented.
format Article
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series Acta Polytechnica CTU Proceedings
spelling doaj-art-767c6db72f274b559fe630acbbc4cd0c2025-08-20T03:14:57ZengCzech Technical University in PragueActa Polytechnica CTU Proceedings2336-53822018-12-01190364510.14311/APP.2018.19.00364299RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGEDaniel VlčekThis project deals with the thermal analyses of the wet and dry storages of the spent nuclear fuel. The dry spent fuel storage sub-channel code COBRA-SFS has been used in order to calculate the temperature field. In this code, the new model of residual heat removal was created for the SKODA 1000/19 cask where the spent nuclear fuel TVSA-T type from NPP Temelin will be stored. The object of calculations was to obtain the inside temperatures under maximum loads. After that, the results were compared to the requirements of the local regulatory body. Because of the absence of experimental data, the validation of the created computational models could not be accomplished. However, according to the verification scheme of the COBRA-SFS authors, the verification of the new models was implemented.https://ojs.cvut.cz/ojs/index.php/APP/article/view/5231Spent nuclear fuel, residual heat removal, dry storages, TVSA-T fuel, thermal analysis, subchannel analysis
spellingShingle Daniel Vlček
RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE
Acta Polytechnica CTU Proceedings
Spent nuclear fuel, residual heat removal, dry storages, TVSA-T fuel, thermal analysis, subchannel analysis
title RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE
title_full RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE
title_fullStr RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE
title_full_unstemmed RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE
title_short RESIDUAL HEAT POWER REMOVAL FROM SPENT NUCLEAR FUEL DURING DRY AND WET STORAGE
title_sort residual heat power removal from spent nuclear fuel during dry and wet storage
topic Spent nuclear fuel, residual heat removal, dry storages, TVSA-T fuel, thermal analysis, subchannel analysis
url https://ojs.cvut.cz/ojs/index.php/APP/article/view/5231
work_keys_str_mv AT danielvlcek residualheatpowerremovalfromspentnuclearfuelduringdryandwetstorage