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Yıl 2015, Cilt: 18 Sayı: 4, 235 - 240, 01.12.2015

Öz

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

Yıl 2015, Cilt: 18 Sayı: 4, 235 - 240, 01.12.2015

Öz

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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Ayrıntılar

Diğer ID JA28CP37AC
Bölüm Araştırma Makalesi
Yazarlar

Ahmad Pırouzmand Bu kişi benim

Fatemeh Mohammadhasanı Bu kişi benim

Yayımlanma Tarihi 1 Aralık 2015
Gönderilme Tarihi 1 Aralık 2015
Yayımlandığı Sayı Yıl 2015 Cilt: 18 Sayı: 4

Kaynak Göster

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. Aralık 2015;18(4):235-240.
Chicago Pırouzmand, Ahmad, ve Fatemeh Mohammadhasanı. “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”. Politeknik Dergisi 18, sy. 4 (Aralık 2015): 235-40.
EndNote Pırouzmand A, Mohammadhasanı F (01 Aralık 2015) Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method. Politeknik Dergisi 18 4 235–240.
IEEE A. Pırouzmand ve F. Mohammadhasanı, “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”, Politeknik Dergisi, c. 18, sy. 4, ss. 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 (Aralık 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 ve Fatemeh Mohammadhasanı. “Multi-Group Neutron Cross Sections and Scattering Matrix Calculations Via Monte Carlo Method”. Politeknik Dergisi, c. 18, sy. 4, 2015, ss. 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.
 
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