방사선 방어시설 구축 시 활용 가능한 관전압별 납 시트 차폐율 성능평가 및 실측 검증
Evaluation and Verification of the Attenuation Rate of Lead Sheets by Tube Voltage for Reference to Radiation Shielding Facilities
- 한국방사선학회
- 한국방사선학회 논문지
- 제17권 제4호
- 2023.08
- 489 - 495 (7 pages)
방사선 방어시설은 진단용 방사선 발생장치가 설치되어 있는 장소에 구축되어 환자, 방사선 작업 종사자 등의 피폭을 방지한다. 본 연구에서는 이러한 방사선 방어시설의 주 재료인 납에 대해 최대관전압별 차폐 두께의 경향성을 몬테칼로 시뮬레이션과 실측을 통해 비교 검증하고자 한다. 몬테칼로 시뮬레이션 코드 중 Monte Carlo N-Particle 6를 활용하였으며 해당 시뮬레이션 상에 모사한 납 차폐 구조도는 선원과 납 시트 사이의 거리는 100 cm, 조사야 크기는 10 × 10 cm2이며 관전압은 80, 100, 120, 140 kVp로 설정하였다. 각 관전압별 에너지 스펙트럼을 산출하여 시뮬레이션에 적용하였다. 80, 100, 120, 140 kVp별 각각 50, 70, 90, 95% 차폐율을 보이는 납 두께를 산출하였다. 80 kVp에서 각 차폐율에 해당하는 두께는 각각 0.03, 0.08, 0.21, 0.33 mm이며, 100 kVp에서는 0.05, 0.12, 0.30, 0.50 mm, 120 kVp에서는 0.06, 0.14, 0.38, 0.56 mm, 140 kVp에서는 0.08, 0.16, 0.42, 0.61 mm로 나타났다. 산출된 납 두께에 대해 실측을 진행하였으며 사용된 방사선 발생장치는 GE Healthcare 사의 Discovery XR 656이며 선량계측기의 경우 IBA 사의 MagicMax이다. 실측 결과 80 kVp에서 각 두께별 차폐율은 43.56, 70.33, 89.85, 93.05%였으며 100 kVp에서는 52.49, 72.26, 86.31, 92.17%, 120 kVp에서는 48.26, 71.18, 87.30, 91.56%, 140 kVp에서는 50.45, 68.75, 89.95, 91.65%.로 나타났다. 시뮬레이션과 실측을 비교한 결과 두 값의 차이가 평균 약 3% 이내로 작은 것으로 확인되었다. 본 연구의 결과는 몬테칼로 시뮬레이션의 신뢰성을 검증함과 동시에 향후 방사선 방어시설의 구축에 있어 기초 데이터로 활용될 수 있을 것으로 사료된다.
Radiation shielding facilities are constructed in locations where diagnostic radiation generators are installed, with the aim of preventing exposure for patients and radiation workers. The purpose of this study is seek to compare and validate the trend of attenuation thickness of lead, the primary material in these radiation shielding facilities, at different maximum tube voltages by Monte Carlo simulations and measurement. We employed the Monte Carlo N-Particle 6 simulation code. Within this simulation, we set a lead shielding arrangement, where the distance between the source and the lead sheet was set at 100 cm and the field of view was set at 10 × 10 cm². Additionally, we varied the tube voltages to encompass 80, 100, 120, and 140 kVp. We calculated energy spectra for each respective tube voltage and applied them in the simulations. Lead thicknesses corresponding to attenuation rates of 50, 70, 90, and 95% were determined for tube voltages of 80, 100, 120, and 140 kVp. For 80 kVp, the calculated thicknesses for these attenuation rates were 0.03, 0.08, 0.21, and 0.33 mm, respectively. For 100 kVp, the values were 0.05, 0.12, 0.30, and 0.50 mm. Similarly, for 120 kVp, they were 0.06, 0.14, 0.38, and 0.56 mm. Lastly, at 140 kVp, the corresponding thicknesses were 0.08, 0.16, 0.42, and 0.61 mm. Measurements were conducted to validate the calculated lead thicknesses. The radiation generator employed was the GE Healthcare Discovery XR 656, and the dosimeter used was the IBA MagicMax. The experimental results showed that at 80 kVp, the attenuation rates for different thicknesses were 43.56, 70.33, 89.85, and 93.05%, respectively. Similarly, at 100 kVp, the rates were 52.49, 72.26, 86.31, and 92.17%. For 120 kVp, the attenuation rates were 48.26, 71.18, 87.30, and 91.56%. Lastly, at 140 kVp, they were measured 50.45, 68.75, 89.95, and 91.65%. Upon comparing the simulation and experimental results, it was confirmed that the differences between the two values were within an average of approximately 3%. These research findings serve to validate the reliability of Monte Carlo simulations and could be employed as fundamental data for future radiation shielding facility construction.
Ⅰ. INTRODUCTION
Ⅱ. MATERIAL AND METHODS
Ⅲ. RESULT
Ⅳ. DISCUSSION
Ⅴ. CONCLUSION
Acknowledgement
Reference