Pre-Conceptual Design of the Research High-Temperature Gas-Cooled Reactor TeResa for Non-Electrical Applications

Eleonora Skrzypek, Dominik Muszyński, Maciej Skrzypek, Piotr Darnowski, Janusz Malesa, Agnieszka Boettcher and Mariusz P. Dąbrowski
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Eleonora Skrzypek: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland
Dominik Muszyński: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland
Maciej Skrzypek: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland
Piotr Darnowski: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland
Janusz Malesa: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland
Agnieszka Boettcher: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland
Mariusz P. Dąbrowski: National Centre for Nuclear Research, A. Sołtana 7, 05-400 Otwock, Poland

Energies, 2022, vol. 15, issue 6, 1-18

Abstract: In line with Polish national activities and research programs investigating non-electrical-reactor use, the national GOSPOSTRATEG-HTR project was launched, aiming at the development of a novel pre-conceptual design of a High-Temperature Gas-cooled Reactor (HTGR). The 40 MW th research reactor would serve as a technology demonstrator for future industrial purposes. In the paper, the proposal of an established thermal-hydraulic and neutronic core design is presented as a result of the National Centre for Nuclear Research team studies, in the scope of the project, including the areas of fluid mechanics, heat exchange and reactor neutronic core design support analyses. The undertaken analyses were confirmed by the series of code investigations involving integral thermal-hydraulic (MELCOR (Sandia National Laboratories, USA), CATHARE (CEA, France)), neutronic (Serpent (VTT, Finland), MCB (AGH University’s Department of Nuclear Energy, Poland)), Computational Fluid Dynamics (ANSYS Fluent (ANSYS, USA)) and others. The calculations performed within the preliminary safety analysis on the pre-concept showed its compliance with international safety standards for the normal operation and Design Basis Accident sequences.

Keywords: HTGR; core design; non-electrical nuclear applications; research reactor (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2022
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