NUCLEAR TECHNIQUES, Volume. 48, Issue 1, 010202(2025)
Simulation analysis of AB-BNCT treatment room shielding based on Monte Carlo geometric splitting variance reduction technique
Figures & Tables(11)
Fig. 3. Schematic view of BNCT treatment room using geometric splitting technique
Fig. 4. Dose rate distribution and relative error at a thickness of 60 cm heavy concrete shielding without variance reduction techniques (color online) (a) Neutron dose rate distribution, (b) Relative error of neutron dose rate distribution, (c) γ-ray dose rate distribution, (d) Relative error of γ-ray dose rate distribution
Fig. 5. Dose rate distribution and relative error at a thickness of 60 cm heavy concrete shielding after using variance reduction techniques (color online) (a) Neutron dose rate distribution, (b) Relative error of neutron dose rate distribution, (c) γ-ray dose rate distribution, (d) Relative error of γ-ray dose rate distribution
Fig. 6. Dose rate under different shielding wall thicknesses (color online) (a) Neutron dose rate, (b) γ-ray dose rate, (c) Total dose rate
Fig. 7. Schematic view of BNCT treatment room after adding lead door 2
Fig. 8. Dose rate under different shielding wall thicknesses after adding lead door 2 (color online)(a) Neutron dose rate, (b) Gamma-ray dose rate, (c) Total dose rate
Table 1. Element composition of boron containing heavy concrete used for shielding
View tableView in ArticleTable 1. Element composition of boron containing heavy concrete used for shielding
成分 Elements 质量百分比 Mass percentage / % H 0.563 B 1.045 O 33.960 F 0.231 Na 1.216 Mg 0.231 Al 0.643 Si 3.326 S 9.193 K 0.101 Ca 6.290 Mn 0.020 Fe 2.200 Zn 0.663 Ba 40.320
Table 2. Dose rate calculation results and relative error in different regions with and without variance reduction technique
View tableView in ArticleTable 2. Dose rate calculation results and relative error in different regions with and without variance reduction technique
区域
Region
未减方差Without variance reduction techniques 减方差With variance reduction techniques 平均中子剂量率
Average neutron dose rate / μSv·h-1
相对误差Relative error / % 平均γ剂量率Average gamma-ray dose rate / μSv·h-1 相对误差Relative error / % 平均中子剂量率Average neutron dose rate/ μSv·h-1 相对误差Relative error / % 平均γ剂量率Average gamma-ray dose rate / μSv·h-1 相对误差Relative error / % A1 4.72×10-3 99.66 6.49×10-1 75.39 1.18×10-2 23.68 5.53×10-1 3.76 A2 1.25×107 47.68 2.11×105 21.97 1.14×107 8.70 1.93×105 1.40 A3 8.78×101 11.51 2.77×102 6.13 8.89×101 1.06 2.78×102 0.49 A4 1.08×104 2.09 4.83×103 0.74 1.08×104 0.80 4.82×103 0.36
Table 3. Dose rate details of D1 to D9 detectors under 60 cm thickness heavy concrete shielding after adding lead door 2
View tableView in ArticleTable 3. Dose rate details of D1 to D9 detectors under 60 cm thickness heavy concrete shielding after adding lead door 2
探测器编号
Detector number
中子剂量率
Neutron dose rate / μSv·h-1
γ剂量率
Gamma-ray dose rate/ μSv·h-1
总剂量率
Total dose rate / μSv·h-1
D1 2.12×10-4 2.14×10-2 2.16×10-2 D2 9.72×10-5 2.29×10-2 2.30×10-2 D3 9.78×10-3 4.68×10-1 4.77×10-1 D4 7.34×10-3 4.70×10-1 4.77×10-1 D5 3.24×10-3 2.26×10-2 2.58×10-2 D6 7.57×10-4 1.97×10-2 2.05×10-2 D7 4.66×10-3 2.22×10-2 2.69×10-2 D8 1.42×10-4 8.40×10-4 9.82×10-4 D9 2.51×10-4 8.94×10-4 1.15×10-3
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Yinan ZHU, Zuokang LIN, Haiyan YU, Xiaohan YU. Simulation analysis of AB-BNCT treatment room shielding based on Monte Carlo geometric splitting variance reduction technique[J]. NUCLEAR TECHNIQUES, 2025, 48(1): 010202
Paper Information
Category: ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS
Received: Dec. 26, 2023
Accepted: --
Published Online: Feb. 26, 2025
The Author Email: LIN Zuokang (林作康)
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