
Radiation measurement of boron neutron capture therapy research facility at T riga Mark-II research reactor Malaysia
Author(s) -
Safwan Shalbi,
N. Sazali,
Muhammad Aliff Ashraff Rosdi,
Faridah Mohamad Idris
Publication year - 2021
Publication title -
iop conference series. materials science and engineering
Language(s) - English
Resource type - Journals
eISSN - 1757-899X
pISSN - 1757-8981
DOI - 10.1088/1757-899x/1106/1/012022
Subject(s) - triga , research reactor , neutron capture , nuclear engineering , boron , electromagnetic shielding , neutron , environmental science , radiochemistry , nuclear physics , medical physics , physics , engineering , chemistry , quantum mechanics
Proper shielding ionizing radiations is a mandatory requirement in all nuclear facilities owing to the harmful effects of radiation on workers and general public. The present work is aimed to measure neutron fluxes and gamma fluxes around the Boron Neutron Capture Therapy (BNCT) research facility at the PUSPATI TRIGA Reactor. This measurement is needed in the subsequent safety assessment so as to ensure the research facility is safely operated