Measurement and calculation of neutron energy spectrum in TRR irradiation facilities: a feasibility study of using TRR for BNCT

Kasesaz, Yaser; Khalafi, Hossein; Rahmani, Faezeh; Ezati, Arsalan; Hosnirokh, Ashkan; Keyvani, Mehdi

Measurement and calculation of neutron energy spectrum in TRR irradiation facilities: a feasibility study of using TRR for BNCT

Document Type : Research Paper

Authors

Yaser kasesaz

Hossein Khalafi

Faezeh Rahmani

Arsalan Ezati

Ashkan Hosnirokh

Mehdi Keyvani

Abstract

An investigation has been made for the use of Tehran Research Reactor (TRR) as a neutron source for the boron neutron capture therapy (BNCT) by calculating and measuring the energy spectrum and spatial distribution of neutrons in all external irradiation facilities, including six beam tubes, thermal column, and medical room. Activation methods with multi-foils and a copper wire have been used for the measurements. The results showed that: (1) small diameter and long length beam tubes cannot provide sufficient neutron flux for the BNCT; (2) for using the medical room, the TRR core should be placed in the open pool position. In this situation, the distance between the core and patient position is about 400 cm, so the neutron flux cannot be sufficient for the BNCT; (3) the best facility which can be adapted for the BNCT application is the thermal column if all graphite blocks can be removed. The non-thermal neutron flux at the beginning of this empty column is 5.33×10⁹ cm^-2 s^-1, where it can provide an appropriate neutron beam for the BNCT.

Keywords

BNCT

Tehran Research Reactor

MCNPX Code

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