Prog Med Phys.  2022 Dec;33(4):53-62. 10.14316/pmp.2022.33.4.53.

Review of Shielding Evaluation Methodology for Facilities Using kV Energy Radiation Generating Devices Based on the NCRP-49 Report

• Kwon NH
• Park HS
• Kim T
• Kim SR
• Kim KB
• Kim JS
• Choi SH
• Kim DW

• KMID: 2537872
• DOI: http://doi.org/10.14316/pmp.2022.33.4.53

Abstract

In this study, we have investigated the shielding evaluation methodology for facilities using kV energy generators. We have collected and analysis of safety evaluation criteria and methodology for overseas facilities using radiation generators. And we investigated the current status of shielding evaluation of domestic industrial radiation generators. According to the statistical data from the Radiation Safety Information System, as of 2022, a total of 7,679 organizations are using radiation generating devices. Among them, 6,299 facilities use these devices for industrial purposes, which accounts for a considerable portion of radiation. The organizations that use these devices evaluate whether the exposure dose for workers and frequent visitors is suitable as per the limit regulated by the Nuclear Safety Act. Moreover, during this process, the safety shields are evaluated at the facilities that use the radiation generating devices. However, the facilities that use radiating devices having energy less than or equal to 6 MV for industrial purposes are still mostly evaluated and analyzed according to the National Council on Radiation Protection and Measurements 49 (NCRP 49) report published in 1976. We have investigated the technical standards of safety management, including the maximum permissible dose and parameters assessment criteria for facilities using radiation generating devices, based on the NCRP 49 and the American National Standards Institute/Health Physics Society N.43.3 reports, which are the representative reports related to radiation shielding management cases overseas.

Keyword

Radiation shielding; Safety; Radiation generator; NCRP 49 report

Figure

• 

  Fig. 1 Transmission coefficient calculation method according to shielding barrier and barrier thickness calculation. Reused from NCRP (Structural shielding design and evaluation for medical use of X-rays and gamma rays of energies up to 10 MeV; 1976. p. 49) [6] with original copyright holder's permission.

• 

  Fig. 2 The status of industrial radiation generator filters sold in Korea. (a) Generators using energy less than or equal to 160 kV. (b) Generators using energy greater than 160 kV and less than or equal to 320 kV.

Reference

References

1. Radiation Safety Management Integrated Information Network. 2022 . Industry/regional licensing information on radioisotopes (RI). Radiation Safety Management Integrated Information Network, 2022;Daejeon: Available from: https://rasis.kins.re.kr/. cited 2022 Nov 29.

2. Nuclear Safety and Security Commission. 2019. Nuclear Safety Commission Notice No. Nuclear Safety and Security Commission, 2019;Seoul: Available from: https://www.law.go.kr/%ED%96%89%EC%A0%95%EA%B7%9C%EC%B9%99/%EB%B0%A9%EC%82%AC%EC%84%A0%EB%B0%A9%ED%98%B8%EB%93%B1%EC%97%90%EA%B4%80%ED%95%9C%EA%B8%B0%EC%A4%80/. cited 2022 Nov 29.

3. Nuclear Safety and Security Commission. 2021. Presidential Decree No. Nuclear Safety and Security Commission, 2021;Seoul: Available from: https://www.law.go.kr/%EB%B2%95%EB%A0%B9/%EC%9B%90%EC%9E%90%EB%A0%A5%EC%95%88%EC%A0%84%EB%B2%95%EC%8B%9C%ED%96%89%EB%A0%B9. cited 2022 Nov 29.

4. Nuclear Safety and Security Commission. 2021. Nuclear Safety Commission Notice No. Nuclear Safety and Security Commission, 2021;Seoul: Available from: https://www.law.go.kr/%ED%96%89%EC%A0%95%EA%B7%9C%EC%B9%99/%EB%B0%A9%EC%82%AC%EC%84%A0%EA%B8%B0%EA%B8%B0%EC%9D%98%EC%84%A4%EA%B3%84%EC%8A%B9%EC%9D%B8%EB%B0%8F%EA%B2%80%EC%82%AC%EC%97%90%EA%B4%80%ED%95%9C%EA%B8%B0%EC%A4%80/. cited 2022 Nov 29.

5. Nuclear Safety and Security Commission. 2019. Nuclear Safety Commission Notice No. Nuclear Safety and Security Commission, 2019;Seoul: Available from: https://www.law.go.kr/%ED%96%89%EC%A0%95%EA%B7%9C%EC%B9%99/%EB%B0%A9%EC%82%AC%EC%84%A0%EC%95%88%EC%A0%84%EB%B3%B4%EA%B3%A0%EC%84%9C%EC%9E%91%EC%84%B1%EC%A7%80%EC%B9%A8/. cited 2022 Nov 29.

6. National Council on Radiation Protection and Measurements (NCRP). 1976. Structural shielding design and evaluation for medical use of X rays and gamma rays of energies up to 10 MeV. NCRP;Bethesda: p. 49.

7. American National Standards Institute (ANSI). 2008; ANSI/HPS N43.3. Installations using non-medical X-ray and sealed gamma-ray sources, energies up to 10 MeV. ANSI. DOI: 10.1007/978-0-387-73003-5_512.

8. National Council on Radiation Protection and Measurements (NCRP). 2006. Structural shielding design and evaluation for megavoltage x-and gamma-ray radiotherapy facilities. NCRP;Bethesda: p. 151.

9. Kelley JP, Trout ED. 1972; Braod-beam attenuation in lead for x rays from 50 to 300 kVp. Radiology. 104:171–175. DOI: 10.1148/104.1.171. PMID: 5033581.

10. Miller W, Kennedy RJ. 1955; X-ray attenuation in lead, aluminum, and concrete in the range 275 to 525 kilovolts. Radiology. 65:920–925. DOI: 10.1148/65.6.920. PMID: 13273659.