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A quasi-static polynomial nodal method for nuclear reactor analysis

Jess C. Gehin
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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992 as discussed by the authors, Boston, Massachusetts, United States of America, Boston, MA
Abstract
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992.

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A time dependent Monte Carlo approach for nuclear reactor analysis in a 3-D arbitrary geometry

TL;DR: In this paper, a dynamic Monte Carlo code named MCSP (Monte Carlo dynamic Simulation of Particles tracking) is developed for both the steady state and time-dependent simulation of particle tracking in an arbitrary 3D geometry.
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A modal multidimensional kinetics method using pseudo-harmonics

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A 3D transport-based core analysis code for research reactors with unstructured geometry

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Nonlinear Iterative Nodal Method Applied to Neutron Flux Modal Analysis

TL;DR: In this article, the authors proposed the correction coupling coefficient modal analysis (CCCMA) method to improve the spatial resolution of the neutron flux modal analyses by including the higher order intra-nodal information through the NLM (Nonlinear Iterative Method)-correction coupling coefficient.