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Information Journal Paper

Title

Design of Esfahan MNSR Vertical Thermal Neutron Beam for Neutron Radiography

Pages

  109-117

Abstract

 In this paper, the MCNPX code is applied for feasibility study of using the Isfahan MNSR as a neutron source to be used for Neutron Radiography. To produce a good neutron beam, in terms of intensity and quality, aluminum (Al) with a thickness of 0. 7 cm, bismuth (Bi), and lead (Pb) with a thickness of 1 cm are used as a fast neutron filter, and the gamma filter, respectively. The L/D ratio of the designed Neutron Radiography facility is 90 and the diverging angle is 2. 1 degree. The thermal neutron flux, the ratio of thermal neutron to gamma dose rate, and the thermal neutron content at the beam exit plane are evaluated to be 1. 47E+05 n/cm2. s, 2. 96E+06 n/cm2. mR, and 92. 5%, respectively. It was realized that if such a thermal neutron beam is built in Isfahan MNSR, many practical and scientific applications of the NR can be realized.

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  • Cite

    APA: Copy

    KHORSANDI, J., ASGARI, A., Kaviani, p., & MOKHTARI, J.. (2018). Design of Esfahan MNSR Vertical Thermal Neutron Beam for Neutron Radiography. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, -(86 ), 109-117. SID. https://sid.ir/paper/97562/en

    Vancouver: Copy

    KHORSANDI J., ASGARI A., Kaviani p., MOKHTARI J.. Design of Esfahan MNSR Vertical Thermal Neutron Beam for Neutron Radiography. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY[Internet]. 2018;-(86 ):109-117. Available from: https://sid.ir/paper/97562/en

    IEEE: Copy

    J. KHORSANDI, A. ASGARI, p. Kaviani, and J. MOKHTARI, “Design of Esfahan MNSR Vertical Thermal Neutron Beam for Neutron Radiography,” JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, vol. -, no. 86 , pp. 109–117, 2018, [Online]. Available: https://sid.ir/paper/97562/en

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