Analysis of Radiation Effects on Workers and Environment Pilot Plant Boron Neutron Capture Therapy (BNCT)

Authors

  • Nur Endah Sari Physics, Faculty of Science and Technology, State Islamic University Sunan Kalijaga
  • Yohannes Sardjono Center of Science and Technology of Accelerator; National Nuclear Energy Agency
  • Andang Widi Harto Departemen Teknik Nuklir Dan Teknik Fisika Fakultas Teknik Universitas Gadjah Mada

DOI:

https://doi.org/10.24246/ijpna.v2i2.75-82

Keywords:

Radiation Protection, BNCT, MCNPX, Radiation Shielding

Abstract

BNCT is a new method in nuclear technology. The aim of BNCT application is to reduce human risk which used to kills cell targeting characteristic. The impact of using this technology should be considered before it is applied, among the effects of radiation on workers and the surrounding environment BNCT pilot plant. A research on modeling of BNCT pilot plant used a collimator for a 30 MeV cyclotron neutron sources which had been designed from the past research. Radiation shielding modeling for treatment room used MCNPX software. The radiation shielding was concrete baryte on each side that includes coated borated polyethylene 2 cm thick and it is featured with a sliding door with dimensions 220 × 87 × 200 cm coated with stainless steels 2 cm thick. Results obtained value equivalent dose rate of neutron and gamma of each 41.5 µSv.h-1 and 2.05 µSv.h-1. Effects of radiation received by workers in the form of deterministic effects did not have a significant are impact.

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References

BAPETEN. (2013). BAPETEN Chairman’s Regulation Number 4 Year 2013. Retrieved from http://jdih.bapeten.go.id/index.php/site/dokview/id/322

BAPETEN. (2015). Instrumentation Radiation Protection Document. Retrieved from http://ansn.bapeten.go.id/

Cember,Herman & Thomas E.Johnson. (2009). Introduction to Health Physics (4th edition). United States: The McGraw-Hill Companies.

Chen, A.Y., Y.W.H.Liu., & R.J.Sheu. (2008). Radiation shielding evaluation of the BNCT treatment room at THOR: A TORT-coupled MCNP Monte Carlo simulation study. Applied Radiation and Isotopes 66, 28-38. doi:10.1016/j.apradiso.2007.07.016

Darsono, Safirudin, & M.Toifur. (2013). Simulation For Radiation Shielding Design Of EBM-Latex Using MCNP5. Ganendra Journal Nuclear Science and Technology, Volume 16, Number 2, 87-96.

Holden,N.E & R.N.Reciniello. (2005). Radiation Dosimetry in the Patient Treatment Room at the BMRR. 12th International Symposium on Reactor Dosimetry ,Gatlinburg,TN ,New York.

Ilma, Muhammad. (2013). Design Of Collimator In The Radial Piercing Beam Port Of Kartini Reactor For Boron Neutron Capture Therapy. Gajah Mada University, Indonesia.

Kobayashi,T., Y. Sakurai., K.Kanda., Y.Fujita., & K.Ono. (2000). The Remodelling outline of neutron irradiation facility of the Kyoto University Research Reactor mainly for neutron capture therapy. Nuclear Technology, 131-141. Retrieved from http: //www.iaea.org/inis/collection/NCLCollectionStore/_Public/32/030/32030427.pdf

Kerr, George D., Joseph V. Pace,III., & Stephen D.Egbert. (2005). Survivor dosimetry Part A “Fluence to kerma conversion coefficients”. Retrieved from http:// inis.iaea.org.

Made.A, I. (2015). Optimization Of Collimator Design For BNCT Based Cyclotron 30 MeV and Its Dosimetry Simulation in Head and Neck Soft Tissue Sarcoma Using Monte Carlo N Particle X Program. Gajah Mada University, Indonesia.

Moss,R.L., F.Stecher-Rasmussen., K.Appelman., A.Roca., & A.Wittig. (2005). Neutron Activation of Patients following BNCT at the HFR Petten. Retrieved from http: https://www.researchgate.net/profile/Finn_StecherRasmussen/publication/267799995_Neutron_Activation_of_Patients_following_BNCT_at_the_HFR_Petten/links/55c09d8308ae9289a09b8b6a.pdf

Saurwien, Wolfgang A.G. (2012). Principles and Roots of Neutron Capture Therapy. Neutron Capture Therapy Principles and Application, 1-16. New York: Springer-Verlag Berlin Heidelberg.

Tanaka, Gi-ichiro and Hisao Kawamura. (2000). Reference Man Models on Normal Data from Human Populations. Retrieved from http://www.irpa.net/irpa10/cdrom/00602.pdf

Turner,James.E. (2007). Atoms, Radiation, and Radiation Protection (3rd edition). Jerman: WILEY.

Wahyuningsih, Dwi. (2014). Optimation Of Collimator Design For In Vivo Testing Of Boron Neutron Capture Therapy (BNCT) On Radial Piercing Beam Port Kartini Nuclear Reactor Using Monte Carlo N Particle 5 (MCNP5) Simulation. Gajah Mada University, Indonesia.

Widyaningsih,Dewi & Heri Sutanto. (2013). Determination of External Radiation Dose Radiation On Workers At Radiation Room Unit Radiotherapy DR. KARIADI SEMARANG Hospital. Periodic Journal of Physics,Volume 16, Number 2, 57-62. Issn: 1410 – 9662

Wiyuniati,Slamet & Indragini. Proposal of Dose Constraint Value for Radiation Worker and Trainees in Center for Education and Training, National Nuclear Energy Agency.Widyanuklida, Volume 15, Number 1, 46-51.

Wolfgang Sauerwein & Ray Moss. (2009). Requirement for Boron Neutron Capture Therapy (BNCT) at a Nuclear Research Reactor. The European BNCT Project, Belanda.

Wolfgang A.G.Sauerwein, Pierre M. Bet, dan Andrea Wittig. (2012). Neutron Capture Therapy. Drugs for BNCT : BSH and BPA, Neutron Capture Therapy Principles and Application, 117-161. New York: Springer-Verlag Berlin Heidelberg.

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Published

2017-06-30

How to Cite

Sari, N. E., Sardjono, Y., & Harto, A. W. (2017). Analysis of Radiation Effects on Workers and Environment Pilot Plant Boron Neutron Capture Therapy (BNCT). Indonesian Journal of Physics and Nuclear Applications, 2(2), 75–82. https://doi.org/10.24246/ijpna.v2i2.75-82

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