Modelling of thermal hydraulics in a KAROLINA calorimeter for its calibration methodology validation

• Autorzy: Luks A. , Pytel K. , Tarchalski M. , Uzunow N. , Krok T.

Identyfikatory

DOI

10.1515/nuka-2016-0074

• Języki publikacji: EN

Abstrakty

EN

Results of numerical calculations of heat exchange in a nuclear heating detector for nuclear reactors are presented in this paper. The gamma radiation is generated in nuclear reactor during fission and radiative capture reactions as well as radioactive decay of its products. A single-cell calorimeter has been designed for application in the MARIA research reactor in the National Centre for Nuclear Research (NCBJ) in Świerk near Warsaw, Poland, and can also be used in the Jules Horowitz Reactor (JHR), which is under construction in the research centre in Cadarache, France. It consists of a cylindrical sample, which is surrounded by a gas layer, contained in a cylindrical housing. Additional calculations had to be performed before its insertion into the reactor. Within this analysis, modern computational fuid dynamics (CFD) methods have been used for assessing important parameters, for example, mean surface temperature, mean volume temperature, and maximum sample (calorimeter core) temperature. Results of an experiment performed at a dedicated out-of-pile calibration bench and results of numerical modelling validation are also included in this paper.

Słowa kluczowe

EN

computional fluid dynamics; CFD; differential calorimeter; gamma heating; gamma rays; Jules Horowitz Reactor; JHR; modelling of thermal hydraulics; nuclear heating; nuclear reactor; research; reactor MARIA

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2016
• Tom: Vol. 61, No. 4
• Strony: 453--460
• Opis fizyczny: Bibliogr. 3 poz., rys.

Twórcy

autor

Luks A.

• Innovative Nuclear and Sustainable Power Engineering, Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Str., 00-665 Warsaw, Poland, Tel.: [phone]

autor

Pytel K.

• National Centre for Nuclear Research, 7 Andrzeja Sołtana Str., 05-400 Otwock/Swierk, Poland

autor

Tarchalski M.

• National Centre for Nuclear Research, 7 Andrzeja Sołtana Str., 05-400 Otwock/Swierk, Poland

autor

Uzunow N.

• Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Str., 00-665 Warsaw, Poland

autor

Krok T.

• National Centre for Nuclear Research, 7 Andrzeja Sołtana Str., 05-400 Otwock/Swierk, Poland

Bibliografia

• 1. Kiełkiewicz, M. (1990). Pomiary w reaktorach jądrowych. Warszawa: WNT.
• 2. Wiśniewski, S ., & Wiśniewski, T. S. (2009). Wymiana ciepła. Warszawa: WNT.
• 3. ANSYS Inc. (2011). ANSYS fl uent theory guide. Release 14.0. Southpointe: ANSYS, Inc.

Uwagi

PL

Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę.