A quasi-static polynomial nodal method for nuclear reactor analysis
TLDR
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992 as discussed by the authors, Boston, Massachusetts, United States of America, Boston, MAAbstract:
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992.read more
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Dissertation
Discontinuous space-time dependent nodal synthesis method for reactor analysis
TL;DR: In this article, the authors investigated the accuracy and efficiency of a nodal synthesis method for steady-state and transient reactor analysis using DISCOVER (DIscontinuous Synthesis COde for VERification) computer code.
Journal ArticleDOI
Correcting the Cusping Problem in Three-Dimensional Transients through NEM Modification
Zelmo Rodrigues de Lima,Aquilino Senra Martinez,Fernando de C. da Silva,Antonio Carlos Marques Alvim +3 more
TL;DR: In this article, an alternative method based on the nodal expansion method was introduced to deal with partially inserted control rods in nodes, which was evaluated in a transient problem and gave satisfactory results and corrected the cusping effect in the case analyzed in this technical note.
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Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code
TL;DR: In this article, a new time-dependent transport approach is described to simulate the nuclear reactor dynamic correctly using the MCNPX code, and the fundamental parameters of a nuclear reactor like multiplication factor (Keff) and mean generation time (tG) are calculated using MC NPX code.
Journal ArticleDOI
A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback
TL;DR: A time-dependent code namely MCNP-NOD (MCNPX code based on a NODal discretization) was developed for solving time- dependent transport equation in an arbitrary geometry considering feed backs and is able to simulate multi-group processes using appropriate libraries.
Journal ArticleDOI
Higher order compact finite difference schemes for steady and transient solutions of space–time neutron diffusion model
TL;DR: In this article , the authors proposed higher order compact finite difference schemes to approximate the neutron leakage terms by using concentrated points around a central point instead of minimizing the mesh spacing taking into account the location of the diffusion coefficients.