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

Ahmad PIROUZMAND; Fatemeh MOHAMMADHASANI

Makale detayları

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

Yazarlar:

Ahmad PIROUZMAND | Fatemeh MOHAMMADHASANI

Yayıncı:

Gazi University

Dergi:

Journal of Polytechnic 2015 Vol.18 Issue 4, pp.235-240

Belge Tipi:

Makale

Yayın Tarihi:

11/2015

Belge Dili:

Türkçe

Document ID (Org No.):

2000591530

Sıklık:

Aylık

eISSN:

2147-9429

Özet:

 

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.

Makale detayları

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

Yazarlar: Ahmad PIROUZMAND | Fatemeh MOHAMMADHASANI

Yayıncı: Gazi University

Dergi: Journal of Polytechnic 2015 Vol.18 Issue 4, pp.235-240

Belge Tipi: Makale

Yayın Tarihi: 11/2015

Belge Dili: Türkçe

Document ID (Org No.): 2000591530

Sıklık: Aylık

eISSN: 2147-9429

Sayı

Yazarlar:

Ahmad PIROUZMAND | Fatemeh MOHAMMADHASANI

Yayıncı:

Gazi University

Dergi:

Journal of Polytechnic 2015 Vol.18 Issue 4, pp.235-240

Belge Tipi:

Makale

Yayın Tarihi:

11/2015

Belge Dili:

Türkçe

Document ID (Org No.):

2000591530

Sıklık:

Aylık

eISSN:

2147-9429