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Year 2015, Volume: 18 Issue: 4, 235 - 240, 01.12.2015

Abstract

Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method

Year 2015, Volume: 18 Issue: 4, 235 - 240, 01.12.2015

Abstract

This study describes a new methodology to estimate multi-group neutron cross sections and scattering matrix elements from a Monte Carlo simulation, particularly from MCNPX 2.7 code. The geometric flexibility associated with the Monte Carlo method makes it very suitable for the generation of highly accurate multi-group constants. While the deterministic lattice codes are not capable of dealing with energy as a continuous variable the Monte Carlo codes such as MCNPX make use of a continuous energy cross sections data for neutron transport calculations. To determine the scattering matrix, an output file of a MCNPX run (socalled PTRAC file) with all relevant source, collision and terminal events of the simulation is used. First, by a separately special program in MATLAB, the PTRAC file is read and tracks are selected in the geometrical region for which one wants to calculate the multi-group constants. Then, information such as coordinates of the particle position, particle direction with coordinates axes, energy and weight of the particle are extracted. The multi-group scattering matrix elements are generated via the weight-to-flux ratio method using the above data available in the PTRAC file. The proposed method is validated using three benchmark problems involve a slab, a pin cell, and a fuel assembly of Tehran research reactor (TRR). The generated multi-group constants via presented method and multiplication factor calculation presents a good comparison to the reference values

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Details

Other ID JA28CP37AC
Journal Section Research Article
Authors

Ahmad Pırouzmand This is me

Fatemeh Mohammadhasanı This is me

Publication Date December 1, 2015
Submission Date December 1, 2015
Published in Issue Year 2015 Volume: 18 Issue: 4

Cite

APA Pırouzmand, A., & Mohammadhasanı, F. (2015). Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method. Politeknik Dergisi, 18(4), 235-240.
AMA Pırouzmand A, Mohammadhasanı F. Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method. Politeknik Dergisi. December 2015;18(4):235-240.
Chicago Pırouzmand, Ahmad, and Fatemeh Mohammadhasanı. “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”. Politeknik Dergisi 18, no. 4 (December 2015): 235-40.
EndNote Pırouzmand A, Mohammadhasanı F (December 1, 2015) Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method. Politeknik Dergisi 18 4 235–240.
IEEE A. Pırouzmand and F. Mohammadhasanı, “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”, Politeknik Dergisi, vol. 18, no. 4, pp. 235–240, 2015.
ISNAD Pırouzmand, Ahmad - Mohammadhasanı, Fatemeh. “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”. Politeknik Dergisi 18/4 (December 2015), 235-240.
JAMA Pırouzmand A, Mohammadhasanı F. Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method. Politeknik Dergisi. 2015;18:235–240.
MLA Pırouzmand, Ahmad and Fatemeh Mohammadhasanı. “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”. Politeknik Dergisi, vol. 18, no. 4, 2015, pp. 235-40.
Vancouver Pırouzmand A, Mohammadhasanı F. Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method. Politeknik Dergisi. 2015;18(4):235-40.