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Cyclotron 30 MeV 1.5 mA shielding design for boron neutron capture therapy
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A.R.W. Wicaksana   , A. Muharini , Y. Sardjono , G.S. Wijaya , Z. Ismail , I.M. Triatmoko , S. Ulya , H. Prasetio , N. Nuraeni , N.R. Hidayati , Fendinugroho , Y. Kasesaz |
| Research Center for Safety, Metrology, and Nuclear Quality Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency Indonesia , syar015@brin.go.id |
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Abstract: (9 Views) |
Background: Effective radiation shielding in Boron Neutron Capture Therapy (BNCT) facilities is essential to protect patients, staff, and the environment from secondary radiation. This study aims to determine the optimal thickness of Portland, boron, and barite concretes for shielding the Beam Shaping Assembly (BSA) in BNCT facilities, ensuring compliance with International Atomic Energy Agency (IAEA) and Indonesia’s BAPETEN (Nuclear Energy Regulatory Agency of Indonesia) safety standards. Materials and Methods: Monte Carlo simulations were performed using the Particle and Heavy Ion Transport Code System (PHITS) to model radiation interactions. The shielding performance of the three concretes was evaluated across five critical areas of the BSA: front, left side, external labyrinth, top, and bottom, utilizing 100,000,000 particles for statistical accuracy. Results: Barite concrete required the least thickness due to its high density and superior photon attenuation, with optimal thicknesses of 0.56 m, 0.4 m, 1.0 m, 0.4 m, and 0.32 m in the respective areas. Boron concrete provided enhanced neutron protection with thicknesses of 0.79 m, 0.35 m, 1.0 m, 0.45 m, and 0.32 m. Portland concrete, while needing greater thickness for gamma shielding, remained cost-effective and accessible with thicknesses of 0.7 m, 0.5 m, 1.0 m, 0.5 m, and 0.37 m. Conclusion: All three concretes met IAEA and BAPETEN safety standards. Barite concrete was most effective for photon attenuation, boron concrete excelled in neutron protection, and Portland concrete offered a practical balance between effectiveness and cost. These findings aid in designing safe and efficient BNCT facilities, especially in resource-limited settings. |
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| Keywords: BNCT, radiation shielding, Monte Carlo simulation, PHITS, concrete materials. |
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Full-Text [PDF 947 kb]
(3 Downloads)
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Type of Study: Original Research |
Subject:
Radiation Biology
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