A new Monte Carlo approach for solution of the time dependent neutron transport equation based on nodal discretization to simulate the xenon oscillation with feedback
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference15 articles.
1. A Quasi-Static Polynomial Nodal Method for Nuclear Reactor Analysis. Ph.D. thesis;Gehin,1992
2. A Time-Dependent, Three-Dimensional Neutron Transport Methodology;Goluoglu;Nucl. Sci. Eng.,2001
3. Scouting the feasibility of Monte Carlo reactor dynamics simulations;Legrady,2008
4. A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback;Mazaher;Ann. Nucl. Energy,2019
5. A time dependent Monte Carlo approach for nuclear reactor analysis in a 3-D arbitrary geometry;Mazaher;Progr. Nucl. Energy,2019
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1. Modification of a Dynamic Monte Carlo Technique to Simplify and Accelerate Transient Analysis with Feedback;Nuclear Science and Engineering;2021-11-22
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