Document Type : Research paper
Authors
Department of Energy Engineering, Sharif University of Technology, P.O.Box: 1136-9363, Tehran, Iran
Abstract
Improvement of reactor safety using simulation and analysis of the power reactor noise needs to develop the neutron noise computation codes. The purpose of the current study is to develop the neutron noise simulator for hexagonal geometry reactors. Therefore, in this research, the SD-HACNEM (Sharif Dynamic - High order Average Current Nodal Expansion Method) simulator is improved to solve the steady-state neutron diffusion equation and neutron noise equation in the frequency-domain for two-dimensional hexagonal geometry by the high-order nodal expansion method. Firstly, calculation is performed for the steady-state. To reduce the discretization error, the flux expansion polynomials degree is increased from 3rd to 5th by considering the nodes with the size of a fuel assembly for either ACNEM (Average Current Nodal Expansion Method) or HACNEM (High-order Average Current Nodal Expansion Method). The verification of the ACNEM and HACNEM is performed by comparing the results with valid references for the IAEA-2D benchmark problem reactor. The steady-state numerical results show that the use of HACNEM provides more accuracy compared with ACNEM, without reducing the size of the nodes. In the main part of the present study, neutron noise calculations are performed in the frequency-domain for two types of noise sources including absorber with variable strength and ILOFAIP . The results are benchmarked by performing simulation at zero frequency and adjoint calculations. The numerical results show that the use of the high-order nodal expansion method is effective for the simulation of neutron noise in the hexagonal reactor.
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- Olmo-Juan N, Demazière C, Barrachina T, Miró R, Verdú G. PARCS vs CORE SIM neutron noise simulations. Progress in Nuclear Energy. 2019;115:169-80. doi: 1016/j.pnucene.2019.03.041.
- Demazière C, Pázsit I. Power reactor noise, lecture notes. Department of Nuclear Engineering, Chalmers University of Technology, Gothenburg, Sweden. 2008.
- Hosseini SA. High accurate three-dimensional neutron noise simulator based on GFEM with unstructured hexahedral elements. Nuclear Engineering and Technology. 2019. doi: 10.1016/j.net.2019.04.006.
- Petkov G. Symptom-based context quantification for dynamic accident analysis. Safety science. 2020;121:666-78. doi: 10.1016/j.ssci.2018.02.027.
- Demazière C, Andhill G. Identification and localization of absorbers of variable strength in nuclear reactors. Annals of Nuclear Energy. 2005;32(8):812-42. doi: /10.1016/j.anucene.2004.12.011.
- Demazière C. Development of a 2-D 2-group neutron noise simulator. Annals of Nuclear Energy. 2004;31(6):647-80. doi: 10.1016/j.anucene.2003.08.007.
- Larsson V, Demazière C, Pázsit I, Tran HN. Neutron noise calculations using the Analytical Nodal Method and comparisons with analytical solutions. Annals of Nuclear Energy. 2011;38(4):808-16. doi: 10.1016/j.anucene.2010.11.017.
- Malmir H, Vosoughi N, Zahedinejad E. Development of a 2-D 2-group neutron noise simulator for hexagonal geometries. Annals of Nuclear Energy. 2010;37(8):1089-100. doi: 10.1016/j.anucene.2010.04.007.
- Hosseini SA, Vosoughi N, Vosoughi J. Neutron noise simulation using ACNEM in the hexagonal geometry. Annals of Nuclear Energy. 2018;113:246-55. doi: 10.1016/j.anucene.2017.11.037.
- Bahrami M, Vosoughi N. SN transport method for neutronic noise calculation in nuclear reactor systems: Comparative study between transport theory and diffusion theory. Annals of Nuclear Energy. 2018;114:236-44. doi: 10.1016/j.anucene.2017.12.041.
- Hosseini SA, Vosoughi N. Neutron noise simulation by GFEM and unstructured triangle elements. Nuclear Engineering and Design. 2012;253:238-58. doi: 10.1016/j.nucengdes.2012.08.023.
- Chionis D, Dokhane A, Belblidia L, Pecchia M, Girardin G, Ferroukhi H, et al. SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations. Int Conf Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017), Jeju, Korea; 2017.
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How to cite this article A. Kolali, D. Naghavi Dizaji*, M. Ghafari, N. Vosoughi, Development of High-Speed Neutron Noise Simulator based on High order Nodal Expansion Method for Hexagonal Geometry in Frequency-Domain, Journal of Nuclear Research and Applications (JONRA) Volume 4 Number 3 Summer (2024) 33-41. |
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This work is licensed under the Creative Commons Attribution 4.0 International License. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0. |
- Torres L, Chionis D, Montalvo C, Dokhane A, García-Berrocal A. Neutron Noise Spectral Features of Simulated Mechanical and Thermal-Hydraulic Perturbations in a PWR
Core. EPJ Web of Conferences; 2021: EDP Sciences. doi: 10.1051/epjconf/202124721001.
- Viebach M, Lange C, Kliem S, Demaziere C, Rohde U, Hennig D, et al. Verification of the code DYN3D for calculations of neutron flux fluctuations. Annals of Nuclear Energy. 2022;166:108735. doi: 10.1016/j.anucene.2021.108735.
- Kolali A, Vosoughi J, Vosoughi N. Development of SD-HACNEM neutron noise simulator based on high order nodal expansion method for rectangular geometry. Annals of Nuclear Energy. 2021;162:108496. doi: 10.1016/j.anucene.2021.108496.
- Lawrence RD. DIF3D nodal neutronics option for two-and three-dimensional diffusion theory calculations in hexagonal geometry.[LMFBR]. Argonne National Lab., IL (USA); 1983.
- Finnemann H, Bennewitz F, Wagner M. Interface current techniques for multidimensional reactor calculations. Atomkernenergie. 1977;30(2):123-8.
- Downar T, Lee D, Xu Y, Kozlowski T, Staudenmier J. PARCS v2. 6 US NRC core neutronics simulator theory manual. Purdue University, West Lafayette, IN. 2004.
- Putney JM. Nodal methods for solving the diffusion equation for fast reactor analysis. University of London, 1984.
- Hall S. The development of a nodal method for the analysis of PWR cores with advanced fuels (Doctoral dissertation, Imperial College London). 2013.
- Bell GI, Glasstone S. Nuclear reactor theory. US Atomic Energy Commission, Washington, DC (United States); 1970.
- Chao YA, Shatilla Y. Conformal mapping and hexagonal nodal methods—II: implementation in the ANC-H code. Nuclear Science and Engineering. 1995;121(2):210-25. doi: 10.13182/NSE95-A28559.
- Grundmann U, Hollstein F. A two-dimensional intranodal flux expansion method for hexagonal geometry. Nuclear science and engineering. 1999;133(2):201-12. doi: 10.13182/NSE99-A2082.
- Hebert A. A Raviart–Thomas–Schneider solution of the diffusion equation in hexagonal geometry. Annals of Nuclear Energy. 2008;35(3):363-76. doi: 10.1016/j.anucene.2007.07.016.
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