Thermal-Hydraulic Analysis of TEPLATOR Moderator Cooling System

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F22%3A43967408" target="_blank" >RIV/49777513:23220/22:43967408 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Thermal-Hydraulic Analysis of TEPLATOR Moderator Cooling System
Original language description
The heavy water reactor concept TEPLATOR contains separate independent systems for the primary coolant and the moderator. The present study analyses the low-pressure moderator cooling system of TEPLATOR during full-power operation. The moderator is heated from neutron thermalization, gamma rays’ absorption, fission product decay and decay of activation products. Additionally, heat transfer from the coolant channels has to be taken in the analyses of the moderator cooling system. Preliminary thermal-hydraulic analyses of the cooling system are supplemented by CFD simulations of heat and fluid flow in the moderator vessel, emphasizing flow type regimes. Results from CFD simulations will be further assessed to evaluate and optimize the moderator cooling system with particular attention to inlets and outlets locations.
Czech name
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Czech description
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Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year
2022
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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