An investigation on the improvement of neutron radiography system of the Tehran research reactor by using MCNPX simulations

Moharram Amini; Seyed Mehrdad Zamzamian; Amir Hossein Fadaei; Morteza Gharib; Seyed Amir Hosein Feghhi

Nuclear Engineering and Technology (Oct 2021)

An investigation on the improvement of neutron radiography system of the Tehran research reactor by using MCNPX simulations

Moharram Amini,
Seyed Mehrdad Zamzamian,
Amir Hossein Fadaei,
Morteza Gharib,
Seyed Amir Hosein Feghhi

Affiliations

Moharram Amini: Faculty of Nuclear Engineering and Physics, Amirkabir University of Technology (Tehran Polytechnic), Hafez Street, Tehran, Iran; Young Researchers and Elites Club, Science and Research Branch, Islamic Azad University, Tehran, Iran
Seyed Mehrdad Zamzamian: Department of Energy Engineering, Sharif University of Technology, Tehran, Iran; Department of Radiation Application, Shahid Beheshti University G.C, Tehran, Iran; Corresponding author. Faculty of Nuclear Engineering and Physics, Amirkabir University of Technology (Tehran Polytechnic), Hafez Street, Tehran, Iran.
Amir Hossein Fadaei: Faculty of Nuclear Engineering and Physics, Amirkabir University of Technology (Tehran Polytechnic), Hafez Street, Tehran, Iran
Morteza Gharib: Faculty of Nuclear Engineering and Physics, Amirkabir University of Technology (Tehran Polytechnic), Hafez Street, Tehran, Iran
Seyed Amir Hosein Feghhi: Department of Radiation Application, Shahid Beheshti University G.C, Tehran, Iran

Journal volume & issue: Vol. 53, no. 10
pp. 3413 – 3420

Abstract

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Applying the available neutron flux for medical and industrial purposes is the most important application of research reactors. The neutron radiography system is used for non-destructive testing (NDT) of materials so that it is one of the main applications of nuclear research reactors. One of these research reactors is the 5 MW pool-type light water research reactor of Tehran (TRR). This work aims to investigate on materials and location of the beam tube (BT) of the TRR radiography system to improve the index parameters of BT. Our results showed that a through-type BT with 20 cm thick carbon neutron filter, 1.2 cm and 9.4 cm of the diameter of inlet (D1) and output (D2) BT, respectively gives thermal neutron flux almost 25.7, 5.6 and 1.1 times greater than the former design of the TRR (with D1 = 1.8 cm and D1 = 9.4 cm), previous design of the TRR with D1 = 3 cm and D1 = 9.4 cm, and another design with D1 = 5 cm and D1 = 9.4 cm, respectively. Therefore, the design proposed in this paper could be a better alternative to the current BT of the TRR.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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