Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code-Reference-Cited by-同舟云学术

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Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code

Published:2019-08 Issue: Volume:130 Page:240-249
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Mazaher Meysam Ghaderi,Salehi Ali Akbar,Vosoughi Naser

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Alcouffe, R. E., Baker, R. S., 2005. A Time-Dependent, Parallel Neutral Particle Transport Code System. LANL, LA-UR-05-3925 edition.

2. The verification of 3 dimensional nodal kinetics code ANCK using transient benchmark problems;Aoki;Nucl. Sci. Technol.,2007

3. A Quasi-Static Polynomial Nodal Method for Nuclear Reactor Analysis;Gehin,1992

4. A time-dependent, three-dimensional neutron transport methodology;Goluoglu;Nucl. Sci. Eng.,2001

5. A Time-dependent Method of Characteristics Formulation with Time Derivative Propagation;Hoffman,2013

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Transient Monte Carlo simulations with OpenMC(TD): A catalyst towards advancing research in next-generation reactors and to improve fission nuclear data;Nuclear Engineering and Design;2024-07

2. Modification of a Dynamic Monte Carlo Technique to Simplify and Accelerate Transient Analysis with Feedback;Nuclear Science and Engineering;2021-11-22

3. 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;Annals of Nuclear Energy;2020-06

4. A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback;Annals of Nuclear Energy;2019-11

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