CFD analysis of the safety related thermal hydraulic parameters describing a flow domain of an experimental medical installation (BNCT converter) inside of the Research Reactor MARIA

  • Piotr Andrzej Prusiński National Centre for Nuclear Research (NCBJ)
  • Sławomir Potempski National Centre for Nuclear Research (NCBJ)
  • Mieczysław Borysiewicz National Centre for Nuclear Research (NCBJ)
  • Karol Kowal National Centre for Nuclear Research (NCBJ)
  • Tomasz Kwiatkowski National Centre for Nuclear Research (NCBJ)
  • Andrzej Marcin Prusiński Institute of Heat Engineering, Warsaw University of Technology

Abstract

The Boron-Neutron Capture Therapy (BNCT) is an experimental radiotherapy technique used to treat the most aggressive types of brain tumors that cannot be surgically removed from the human body. To date, clinical trials of BNCT have been initiated at only a handful of reactors around the world, but advanced studies on BNCT are still being carried out in numerous research centers where the suitable or convertible reac­tors are available. Construction of BNCT facilities is justified only at some existing reactors. Others can possibly be adapted for BNCT by using fission converters to modify the energy spectrum of the primary neutron beam, which makes it useful for treatment purposes. The BNCT converter, designed for use in the MARIA research reactor at the National Centre for Nuclear Research [W1] (NCBJ) in Świerk near Warsaw, Poland, consists of 99 fuel rods (containing low-enriched uranium) inside of the aluminum box. Since its installation affects the core layout and possibly may affect the normal operating regime of the reactor, additional safety analyses must be performed to prove the existence of suffi­cient safety margins. In this study modern Computational Fluid Dynamics (CFD) techniques have been applied to assess the maximum temperature of the rod wall surfaces, the temperature difference between the inlet and outlet of the converter channel, as well as the maximum and average velocity of the fluid and to compare them with the results presented in the reference analytical study. According to  [W1]http://ncbj.gov.pl/en

Author Biographies

Piotr Andrzej Prusiński, National Centre for Nuclear Research (NCBJ)
Senior Specialist at Nuclear Energy Division National Centre for Nuclear Research (NCBJ)
Andrzej Marcin Prusiński, Institute of Heat Engineering, Warsaw University of Technology
Student at Warsaw University of Technology

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Published
2012-12-20
How to Cite
PRUSIŃSKI, Piotr Andrzej et al. CFD analysis of the safety related thermal hydraulic parameters describing a flow domain of an experimental medical installation (BNCT converter) inside of the Research Reactor MARIA. Journal of Power Technologies, [S.l.], v. 92, n. 4, p. 227--240, dec. 2012. ISSN 2083-4195. Available at: <https://papers.itc.pw.edu.pl/index.php/JPT/article/view/351>. Date accessed: 03 dec. 2024.
Section
Nuclear Fuels and Reactor Safety

Keywords

CFD; research reactor MARIA; safety limits; BNCT; fission converter; Świerk Computing Centre

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