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

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F18%3A00325529" target="_blank" >RIV/68407700:21340/18:00325529 - isvavai.cz</a>

Výsledek na webu

<a href="https://ojs.cvut.cz/ojs/index.php/APP/article/view/5231" target="_blank" >https://ojs.cvut.cz/ojs/index.php/APP/article/view/5231</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.14311/APP.2018.19.0036" target="_blank" >10.14311/APP.2018.19.0036</a>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

21100 - Other engineering and technologies

Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2018

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Student Conference on Nuclear Engineering Šimáně 2018

ISBN

978-80-01-06520-4

ISSN

—

e-ISSN

2336-5382

Počet stran výsledku

10

Strana od-do

36-45

Název nakladatele

Czech Technical University in Prague

Místo vydání

Praha

Místo konání akce

FJFI, ČVUT v Praze

Datum konání akce

25. 6. 2018

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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