DETERMINATION OF THE TENTH VALUE LAYER OF LEAKAGE RADIATION ATTENUATION FROM MEDICAL LINEAR ACCELERATORS WITH THE ENERGY OF 6 MEV

Authors

  • Dmytro BIELYKH State Enterprise “State Scientific and Technical Center for Nuclear and Radiation Safety”, Kyiv, Ukraine https://orcid.org/0000-0002-5782-9827
  • Tetiana LYTVYNSKA State Enterprise “State Scientific and Technical Center for Nuclear and Radiation Safety”, Kyiv, Ukraine https://orcid.org/0000-0002-3308-8526
  • Vitalii POLUDNENKO State Enterprise “State Scientific and Technical Center for Nuclear and Radiation Safety”, Kyiv, Ukraine https://orcid.org/0000-0002-8307-6777
  • Olha SITNIKOVA State Enterprise “State Scientific and Technical Center for Nuclear and Radiation Safety”, Kyiv, Ukraine https://orcid.org/0000-0002-0602-9731

DOI:

https://doi.org/10.17721/3041-1491/2024.11-16

Keywords:

tenth-value attenuation layer, linear accelerator, radiation safety, shielding, Monte Carlo method

Abstract

Introduction. The article addresses the significant differences observed in the tenth-value layers (TVL) of leakage radiation attenuation in concrete for medical linear accelerators (linacs) between internationally recognized methodologies of the National Council on Radiation Protection and Measurements (NCRP) and the International Atomic Energy Agency (IAEA).

Methods. These differences have implications for the biological protection calculations. The study aims to determine the TVL for leakage radiation from 6 MeV medical linacs using the Monte-Carlo method.

Results. The study identifies that for an average concrete wall thickness of 1.5 meters, the TVL equals approximately 273.69 mm.

Conclusions. This value 273.69 mm is consistent with the IAEA's value of 279 mm. The study's findings provide a more realistic TVL value for leakage radiation, which aligns closely with the IAEA's data, thus offering a reliable reference for designing radiation protection in medical facilities using linacs.

 

References

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IAEA. (2006). Radiation Protection in the Design of Radiotherapy Facilities. Safety Reports Series No. 47.

 

ICRP. (2010). Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures. Publication 116, Ann. ICRP 40(2-5).

 

NCRP Report 151. (2006). Structural shielding design and evaluation for megavoltage X- and gamma-ray radiotherapy facilities. Journal of Radiological Protection, 26(3), 349. https://doi.org/10.1088/0952-4746/26/3/b01

 

Sato, T., Iwamoto, Y., Hashimoto, S., Ogawa, T., Furuta, T., Abe, S., Kai, T., Matsuya, Y., Matsuda, N., Hirata, Y., Sekikawa, T., Yao, L., Tsai, P.E., Hunter, H.N., Iwase, H., Sakaki, Y., Sugihara, K., Shigyo, N., Sihver, L., & Niita, K. (2024). Recent improvements of the Particle and Heavy Ion Transport code System – PHITS version 3.33. J. Nucl. Sci. Technol., 61, 127–135.

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Published

2025-01-26

How to Cite

BIELYKH, D., LYTVYNSKA, T., POLUDNENKO, V. ., & SITNIKOVA, O. (2025). DETERMINATION OF THE TENTH VALUE LAYER OF LEAKAGE RADIATION ATTENUATION FROM MEDICAL LINEAR ACCELERATORS WITH THE ENERGY OF 6 MEV. The Conference Proceedings “Medical Physics – the Current Status, Problems, the Way of Development. Innovation technologies”, 1(1), 131-138. https://doi.org/10.17721/3041-1491/2024.11-16