On the starting and operational transients at the core of the RMB based on 2D multigroup diffusion
DOI:
https://doi.org/10.15392/2319-0612.2022.1993Palabras clave:
Multigroup Diffusion, Space Kinetics, Thermal Hydraulics, Data VisualizationResumen
RMB is a multipurpose reactor to be built by CNEN. As a multipurpose facility, unlike a nuclear power plant, some operations may result in transients, whether during the movement of materials from remote irradiation, extraction of neutrons through beam holes, reactor starting up, control rod accident, etc. For that, a methodology to visualize some variables like neutron fluxes, temperatures, power, etc., was developed. In this one present some preliminary results based on multigroup diffusion theory, thermal hydraulics feedbacks, and numerical methods, systematized in the DINUCLE code. DINUCLE couples a numerical code of multigroup spatial kinetics, for calculations of the flux of neutrons in the core of reactors, with a numerical code for the analysis of thermo hydraulic transients in rods and plates, considering the refrigerant always single-phase. Use was made of a programming in VBA (Visual Basic for Applications) from Excel, for data visualization in the transient.
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CNEN/DPD/RMB Cálculos iterativos neutrônica/termo-hidráulica para determinar a potência do reator no início de vida. RMB-10100-RD-007, 2010.
STACEY, W. M. Nuclear Reactor Physics, Second Edition: John Wiley, 2004.
DOS SANTOS, R. S. Dynamics of Nuclear Reactor Cores based on One and TwoDimensional Multigroup Diffusion Theory , X ENFIR, 1995.
DOS SANTOS, R. S. Solução Numérica das Equações da Cinética de Reatores com o Método Explicito de Direções Alternadas (ADE), Comunicação Técnica, CNEN/IEN-35, 1992.
MELO, M. AND TOSTES, R. Criando MACROS com o VBA, Alta Books Editora, Rio de Janeiro, 2017.
OriginLab Releases Origin 8.5.1 and OriginPro 8.5.1. NORTHAMPTON, MA (April 27, 2011). Available at: < Origin 8.5 Press Release (originlab.com)>. Last accessed: January 31, 2022.
DOS SANTOS, R. S., SIRER – Um programa para cálculos de transientes num canal médio do núcleo de reatores, Comunicação Técnica, Instituto de Engenharia Nuclear, Rio de Janeiro, 1995.
REED, W. H., Finite Difference Techniques for the Solution of the Reactor Kinetics Equations, ScD Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology, 1969.
REED, W. H. AND K. F. HANSEN, Alternating Direction Methods for the Reactor Kinetics Equations, Nuclear Science Engineering, 41, 431, 1970.
YASINSKY, J. B. AND HENRY A. F., TWIGL – A Program to Solve the TwoDimensional, Two-Group, Space-Time Neutron Diffusion Equations with Temperature Feedback, WAPD-TM-743, February, 1968.
Dos Santos. ● Braz. J. Rad. Sci. ● 2022 22
Benchmark on Beam Interruptions in an Accelerator-driven System: Final Report on Phase II Calculations, http://www.nea.fr/html/science/docs/2004/nsc-doc2004-7.pdf (2004).
DOS SANTOS, R. S. AND MAIORINO, J. R., On the Application of SIRER-ADS in the Simulation of Transients in Accelerator Driven System (ADS), 2007 International Atlantic Conference – INAC 2007, Santos, SP, Brazil, 2007.
HENRY, A. F. AND A. V. VOTA, Some Numerical Experiments Concerning Space-Time Reactor Kinetics Behavior, Nuclear Science Engineering, 22, 171, 1965.
ALCÂNTARA, H. G., PRATI, A., ROSA, M. A. P. AND NAIR, R. P. K., Um Código Unidimensional de Solução de Equações de Cinética Multigrupo, 5o ENFIR, 1, 164, Rio de Janeiro, 1985 .
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Derechos de autor 2022 Brazilian Journal of Radiation Sciences (BJRS)

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