DOSE ESTIMATION OF THE BNCT WATER PHANTOM BASED ON MCNPX COMPUTER CODE SIMULATION

Amanda Dhyan Purna Ramadhani, Susilo Susilo, Irfan Nurfatthan, Yohannes Sardjono, Widarto Widarto, Gede Sutresna Wijaya, Isman Mulyadi Triatmoko

DOI: http://dx.doi.org/10.17146/tdm.2020.22.1.5780

Abstract


Cancer is a malignant tumor that destroys healthy cells. Cancer treatment can be done by several methods, one of which is BNCT. BNCT uses 10B target which is injected into the human body, then it is irradiated with thermal or epithermal neutrons. Nuclear reaction will occur between boron and neutrons, producing alpha particle and lithium-7. The dose is estimated by how much boron and neutron should be given to the patient as a sum of number of boron, number of neutrons, number of protons, and number of gamma in the reaction of the boron and neutron. To calculate the dose, the authors simulated the reaction with Monte Carlo N Particle-X computer code. A water phantom was used to represent the human torso, as 75% of human body consists of water. Geometry designed in MCNPX is in cubic form containing water and a cancer cell with a radius of 2 cm. Neutron irradiation is simulated as originated from Kartini research reactor, modeled in cylindrical form to represent its aperture. The resulting total dose rate needed to destroy the cancer cell in GTV is 2.0814×1014 Gy.s (76,38%) with an irradiation time of 1,4414×10-13 s. In PTV the dose is 5.2295×1013 Gy.s (19,19%) with irradiation time of 5.7367×10-13 s. In CTV, required dose is 1.1866×1013 Gy.s (4,35%) with an irradiation time of 2.5283×10-12 s. In the water it is 1.9128×1011 Gy.s (0,07%) with an irradiation time of 1,5684×10-10 s. The irradiation time is extremely short since the modeling is based on water phantom instead of human body.

Keywords: BNCT, Dose, Cancer, Water Phantom, MCNPX


Full Text:

PDF

References


  1. National Cancer Institute. What is cancer? Understanding Cancer. Accesed form: https://www.cancer.gov/aboutcancer/understanding/what-is-cancer, 2 September 2019
  2. Shahban, M., Hussain, B., Mehmood, K., & Rehman, S. U.Estimation of peripheral dose from Co60 beam in water phantom measured in Secondary Standard Dosimetry Laboratory, Pakistan. Reports of Practical Oncology and Radiotherapy, 22(3), 212–216. 2017
  3. Rosidah, S., Sardjono, Y., & Sumardi, Y.. Dose Analysis of Boron Neutron Capture Therapy (BNCT) At Skin Cancer Melanoma Using MCNPX With Neutron Source from Thermal Column of Kartini. Indonesian Journal of Physics and Nuclear Applications, 2(3), 111–123. 2017
  4. [5] Satoh, D., Kajimoto, T., Shigyo, N., Itashiki, Y.,
  5. Imabayashi, Y., Koba, Y., Uozumi, Y. (2016). Distributions of neutron yields anddoses around a water phantom bombardedwith 290-MeV/nucleon and 430-MeV/nucleon carbon ions. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 387,10–19.
  6. Pozzi, E. C. C., Cardoso, J. E., Colombo, L. L., Thorp, S., Hughes, A. M., Molinari, A. J., Schwint, A. E.Boron neutron capture therapy (BNCT) for liver metastasis: Therapeutic efficacy in an experimental model. Radiation and Environmental Biophysics, 51(3). 2012.
  7. Tesalonika, A. Dosimetry of in vitro and in vivo Trials in Thermal Column Kartini Reactor for Boron Neutron Capture Therapy (BNCT) facility by using MCNPX Simulator Code. Indonesian Journal of Physics and Nuclear Applications, 1(10), 63–72. 2016.
  8. Sakurai, Y., Tanaka, H., Takata, T., Fujimoto, N., Suzuki, M., Masunaga, S., Maruhashi, A. Advances in boron neutron capture therapy (BNCT) at Kyoto University - From reactor-based BNCT to accelerator-based BNCT. Journal of the Korean Physical Society, 67(1),76–81. 2015.
  9. IAEA Current status of neutron capture therapy. Vienna, Austria:International Atomic Energy Agency: 2001.
  10. Hassanein, A. M., Hassan, M. H., Mohamed, N. M. A., & Abou Mandour, M. A. (2018). An optimized epithermal BNCT beam design for research reactors. Progress in Nuclear Energy, 106 (May 2017), 455–464.
  11. Nuclear Data Center JAEA.accesed form: https://wwwndc.jaea.go.jp/Labo/ncap.html.2019
  12. Ramadhan Valiant Gill S Balle.In Vivo Total Dose Analysis in Mice for BNCT Trial TRIGA Kartini Research Reactor Based Using PHITS. Indonesian Journal of Physics and Nuclear Application. 2019
  13. Wicaksono, A. S., Widiharto, A., & Sardjono, Y. (2016). Internal Dose Analysis for Radiation Worker in Cancer Therapy Based on Boron Neutron Capture Therapy with Neutron Source Cyclotron 30 MeV Using Monte Carlo N Particle Extended Simulator. Indonesian Journal of Physics and Nuclear Applications, 2(2), 91–100.
  14. Paul Sherer Institut .Neutron Matter Interaction. Accesedform:https://www.psi.ch/en/niag/neutron-interaction-with-matter.2019
  15. Aghara, S. K., Sriprisan, S. I., Singleterry, R. C., & Sato, T. (2015). Shielding evaluation for solar particle events using MCNPX, PHITS and OLTARIS codes. Life Sciences in Space Research, 4, 79–91.


Refbacks

  • There are currently no refbacks.


PTKRN Digital Library Ristek Mendeley