@inproceedings{46683df2e5a84044a4ddc5466e483d95,
title = "Development of a production MCNP CANDU 3D full-core model with practical remedies to the issues in deriving reliable tally results",
abstract = "This paper documents the development of a production MCNP model that is equivalent to the production WIMS-AECL/DRAGON/RFSP model for a CANDU full-core problem. The MCNP simulations confirm that the issues such as huge computing resources and large memory requirement, slow fission-source convergence, and fission-source correlation remain challenging in the Monte-Carlo calculation of the CANDU 3D full-core problem with higher dominance ratio. These issues are more challenging for the prediction of tally results (such as channel-power and bundle-power distributions) than the prediction of the k-effective values. In order to obtain a reliable MCNP full-core results, especially the power distributions, new approaches are proposed to remedy the above-mentioned issues in the MCNP modelling and simulation of the CANDU 3D full-core problem. Numerical results demonstrate that the new approaches proposed in this paper are practical in deriving reliable power distributions for the realistic CANDU 3D full-core problem from MCNP with limited computing resources. With the enhanced batch method proposed in this paper, CANDU full-core channel-power distributions are obtained from the MCNP simulations with the relative standard deviation less than 0.3\% in the central high-power region and less than 1.2\% in the peripheral low-power region.",
keywords = "CANDU, Full-Core Analysis, MCNP, Mont Carlo",
author = "W. Shen and J. Hu",
year = "2016",
language = "英语",
series = "Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century",
publisher = "American Nuclear Society",
pages = "531--542",
booktitle = "Physics of Reactors 2016, PHYSOR 2016",
note = "Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016 ; Conference date: 01-05-2016 Through 05-05-2016",
}