Assessment of the Absorbed Dose Components of BNCT Method at the Dalat Research Reactor
Year: 2024
Type: article
Abstract: At the Dalat Nuclear Research Reactor (DNRR) in Vietnam, some calculations and experiments of the Boron Neutron Capture Therapy (BNCT) method have been performed at horizontal channel No. 2 of the DNRR using a phantom. This research used the Monte Carlo N-Particle version 5 (MCNP5) code to simulate and calculate the distribution of absorbed dose components of the BNCT method. The collimator of horizontal neutron channel No. 2 of the DNRR was changed from cylindrical to conical to increase the flux of the neutron beam. Simultaneously, neutron crystal filters corresponding to 20 cm Si and 3 cm Bi are also employed to produce high-purity thermal neutron beams. The thermal neutron flux and absorbed dose components have been computed in a water phantom. The gamma dose from the reactor core of the DNRR can be omitted when calculating the total absorbed dose in the BNCT method.
Author: Dang Quyet Pham, Thi Tu Anh Trinh, Xuan Hai Pham
Language: English
Topic: Boron Compounds in Chemistry
Subfield: Radiology, Nuclear Medicine and Imaging
Field: Medicine
Domain: Health Sciences
Open Access status: green
OpenAlex ID: W6893032397
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