Development of a computer code for neutronic calculations of a hexagonal lattice of nuclear reactor using the flux expansion nodal method | Zendy

Mohammadnia Meysam | Zendy; A. Pazirandeh | Zendy; Mostafa Sedighi | Zendy

Open Access

Development of a computer code for neutronic calculations of a hexagonal lattice of nuclear reactor using the flux expansion nodal method

Author(s) -

Mohammadnia Meysam,

A. Pazirandeh,

Mostafa Sedighi

Publication year - 2013

Publication title -

nuclear technology and radiation protection

Language(s) - English

Resource type - Journals

SCImago Journal Rank - 0.31

H-Index - 16

eISSN - 1452-8185

pISSN - 1451-3994

DOI - 10.2298/ntrp1303237m

Subject(s) - nuclear engineering , neutron flux , code (set theory) , lattice (music) , source code , hexagonal crystal system , nodal , neutron , nuclear data , computer science , physics , computational physics , computational science , nuclear physics , engineering , chemistry , crystallography , programming language , set (abstract data type) , acoustics , anatomy , medicine

The flux expansion nodal method is a suitable method for considering nodalization effects in node corners. In this paper we used this method to solve the intra-nodal flux analytically. Then, a computer code, named MA.CODE, was developed using the C# programming language. The code is capable of reactor core calculations for hexagonal geometries in two energy groups and three dimensions. The MA.CODE imports two group constants from the WIMS code and calculates the effective multiplication factor, thermal and fast neutron flux in three dimensions, power density, reactivity, and the power peaking factor of each fuel assembly. Some of the code's merits are low calculation time and a user friendly interface. MA.CODE results showed good agreement with IAEA benchmarks, i. e. AER-FCM-101 and AER-FCM-001

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