Estimation of neutron and gamma dose in the MNSR research reactor

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Choopan Dastjerdi Mohammad Hosein; MOKHTARI JAVAD

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Paper Information

Journal: Journal of Radiation Safety and Measurement Year:2019 | Volume:8 | Issue:4 (supplement) Page(s): 53-58

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Title

Estimation of neutron and gamma dose in the MNSR research reactor

Author(s)

Choopan Dastjerdi Mohammad Hosein | MOKHTARI JAVAD | Issue Writer Certificate

Keywords

Neutron dosimetryQ2

Gamma dosimetryQ1

MNSR reactorQ2

thermo-luminescence dosimeterQ1

MCNP codeQ2

Abstract

In this study, the neutron and gamma doses in the dry channel and in the internal irradiation site of the Miniature Neutron Source research reactor (MNSR) has been calculated and measured. The MNSR reactor is a light water reactor with a maximum power of 30 kW and equipped with various irradiation facilities, including five irradiated sites, five irradiation sites and a dry channel. The internal irradiation sites have the closest gap to the core of the reactor, with the highest flux and doses available in these locations. Dose calculations have been performed using simulation of the reactor by MCNP computational code and dose measurement using TLD600 and TLD700 thermo-luminescence dosimeters. The experiments have been carried out at both the shutdown and operational status of reactor. In order to validate the computational code, the neutron flux in the internal irradiation site and at the end of the dry channel has been measured by foil activation method and validated by the calculation results. The results of the calculation and measurement of the neutron and gamma doses were in good agreement. The determination of neutron and gamma doses at these sites makes possible such experiments and researches that need to receive a precise amount of neutron and gamma doses.

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APA: Copy

Choopan Dastjerdi, Mohammad Hosein, & MOKHTARI, JAVAD. (2019). Estimation of neutron and gamma dose in the MNSR research reactor. IRANIAN JOURNAL OF RADIATION SAFETY AND MEASUREMENT, 8(4 (supplement) ), 53-58. SID. https://sid.ir/paper/392241/en

Vancouver: Copy

Choopan Dastjerdi Mohammad Hosein, MOKHTARI JAVAD. Estimation of neutron and gamma dose in the MNSR research reactor. IRANIAN JOURNAL OF RADIATION SAFETY AND MEASUREMENT[Internet]. 2019;8(4 (supplement) ):53-58. Available from: https://sid.ir/paper/392241/en

IEEE: Copy

Mohammad Hosein Choopan Dastjerdi, and JAVAD MOKHTARI, “Estimation of neutron and gamma dose in the MNSR research reactor,” IRANIAN JOURNAL OF RADIATION SAFETY AND MEASUREMENT, vol. 8, no. 4 (supplement) , pp. 53–58, 2019, [Online]. Available: https://sid.ir/paper/392241/en

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