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Abrate N, Dulla S, Ravetto P, Saracco P. A Generalized Eigenvalue Formulation for Core-Design Applications. NUCL SCI ENG 2023. [DOI: 10.1080/00295639.2022.2134685] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/18/2023]
Affiliation(s)
- Nicolo’ Abrate
- NEMO group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129 Torino, Italy
| | - Sandra Dulla
- NEMO group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129 Torino, Italy
| | - Piero Ravetto
- NEMO group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129 Torino, Italy
| | - Paolo Saracco
- I.N.F.N., Sezione di Genova, Via Dodecaneso, 33 - 16146 Genova, Italy
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Frequency-domain models in the SP N approximation for neutron noise calculations. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104233] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Adaptive time-step control for modal methods to integrate the neutron diffusion equation. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2020.07.004] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Carreño A, Vidal-Ferràndiz A, Ginestar D, Verdú G. ADAPTIVE TIME-STEP CONTROL FOR THE MODAL METHOD TO INTEGRATE THE MULTIGROUP NEUTRON DIFFUSION EQUATION. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124707010] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
The distribution of the power inside a reactor core can be described by the time dependent multigroup neutron diffusion equation. One of the approaches to integrate this time-dependent equation is the modal method, that assumes that the solution can be described by the sum of amplitude function multiplied by shape functions of modes. These shape functions can be computed by solving a _-modes problems. The modal method has a great interest when the distribution of the power cannot be well approximated by only one shape function, mainly, when local perturbations are applied during the transient. Usually, the shape functions of the modal methods are updated for the time-dependent equations with a constant time-step size to obtain accurate results. In this work, we propose a modal methodology with an adaptive control time-step to update the eigenfunctions associated with the modes. This algorithm improves efficiency because of time is not spent solving the systems to a level of accuracy beyond relevance and reduces the step size if they detect a numerical instability. Step size controllers require an error estimation. Different error estimations are considered and analyzed in a benchmark problem with a out of phase local perturbation.
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Lu Q, Rizwan-uddin. Stability analysis of nuclear-coupled thermal hydraulics for a natural circulation lead-cooled fast reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107747] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Li M, Chen W, Hao J. A quasi-static orthogonal method for solving spatial-time neutron kinetics equations in non-steady processes. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2019.103229] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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