A Treatment Planning Comparison between Intensity Modulated Proton Therapy (IMPT) and Volumetric Modulated Arc Therapy (VMAT) for prostate cancer
Thi Cam Thu Nguyen, Thanh Xuan Le
Sci. Tech. Dev. J.; 25(1):2297-2307
Abstract:
Introduction: We made a comparison between IMPT plans and VMAT plans for ten prostate cancer patients with the analysis of dosimetric quantities and EUD for both target volume and OARs.
Methods: Ten patients planned for VMAT were retrospectively replanned with scanned proton beams. Target and OARs were kept as originally delineated in photon plans with the assumption that the change in dose distribution is acceptable. The prescribed dose to the PTV is 74 Gy using an RBE of 1.1. The optimized VMAT plan of each case was normalized using the PTV coverage value obtained from the optimized IMPT plan. For the PTV and OARs, the dosimetric quantities were analyzed. Moreover, EUD with the exponential parameter a with a 95% confidence level was calculated for both the PTV and OARs.
Results: For the PTV, all the averaged dose metrics, including the mean dose, the median dose and the maximum dose, the HI and the EUD, in the IMPT plans were statistically (p0.05) better than those in the VMAT plans. The dose to the PTV from IMPT plans ranged from 69.14.7 to 79.01.1 Gy (RBE), while that from VMAT plans ranged from 68.0 2.8 to 81.6 1.3 Gy (RBE). The mean dose of 2.6 Gy (RBE) to the body from the IMPT plan was significantly (p=0.007) lower than the mean dose of 5.8 Gy (RBE) from the VMAT plans. For all OARs except for the rectum, in the low-to-medium dose region, the volumes receiving low doses in IMPT plans were statistically (p0.05) lower than those in VMAT plans. The IMPT plans show statistically (p0.05) superior dose sparing of the rectum and bladder in comparison to the VMAT plans at the Dmax, Dmean, and V30Gy indices and at all dosimetric indices.
Conclusions: The results show that the IMPT plans were statistically superior to the VMAT plans for both the PTV and OARs. IMPT plans produced a more homogeneous dose in the PTV. For OARs, the volumes receiving the low doses were statistically lower in IMPT plans than in VMAT plans.
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A simple approach for developing model OF Si(Li) detector in Monte Carlo simulation
Huynh Dinh Chuong, Nguyen Thi Truc Linh, Le Thi Ngoc Trang, Vo Hoang Nguyen, Le Hoang Minh , Chau Thanh Tai, Tran Thien Thanh
Huynh Dinh Chuong, Le Thi Ngoc Trang,Vo Hoang Nguyen,Tran Thien Thanh
Applied Radiation and Isotopes, Available online 10 April 2020, 109179
A refined technique for extracting strontium from water samples and quantifying strontium radioisotopes using a gas flow proportional counter
Phan Long Ho, Vu Tuan Minh, Le Dinh Hung, Le Hoang Minh, Tran Thien Thanh, Dang Van Chinh, Chau Van Tao
Progress in Nuclear Energy 187 (2025) 105856
Abstract:
This study focuses on developing an improved analytical method for determining strontium radioactivity (Sr-89 and Sr-90) in water samples. While the original procedure used high concentrations of acid, requiring more sample processing time and reducing safety and analytical performance, the proposed procedure addresses all the drawbacks of the old method. The new method optimizations include using 65 % HNO3 instead of 90 % HNO3 for safety, reducing separation steps from forty-three to twenty-six to save time and costs, and shortening the century equilibration between Sr-90 and Y-90 to under two weeks. Method validation on sixty-one samples shows the detection limit is 0.035 Bq.L-1, meeting EPA requirements of 0.074 Bq.L-1. Strong linearity (r = 0.999) between spiked and measured activity concentrations was observed in the working range of 0.046–23.371 Bq.L-1 encompasses WHO’s 10 Bq.L-1 limit for Sr-90 in drinking water. Interlaboratory testing of three IAEA samples over 2021–2023 further verifies accuracy. The results indicated that the new method has improved efficiency and safety. That reduced costs and analysis time, demonstrating the method’s suitability for various radioanalytical applications, particularly emergency nuclear scenarios demanding rapid Sr-90 isotope quantification.
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A novel method for calculating number buildup factor in gamma-ray transmission measurements using narrow beam geometry
Huynh Dinh CHUONG , Le Thi Ngoc TRANG, Nguyen Thi Truc LINH, Vo Hoang NGUYEN and Tran Thien THANH
Nuclear Technology and Radiation Protection 2024 Volume 39, Issue 3, Pages: 185-198
Abstract:
In this article, we present a novel method to calculate the number buildup factor for arbitrary materials in gamma-ray transmission measurements using a narrow beam geometry. The MCNP6 code was used to simulate photon transport within a collimated transmission configuration, which included a NaI(Tl) scintillation detector paired with a 137Cs or 60Co radioactive source. From these simulations, the number buildup factor values were computed forvarious materials at gamma-ray energies of 661.7 keV, 1173.2 keV, and 1332.5 keV, with sample thicknesses ranging from 0.1-7.0 cm. At each specific gamma-ray energy and material, the number buildup factor values exhibited a strong linear relationship with the sample thickness. Furthermore, the slope of these linear relationships can be expressed as a product of mass density and a cubic polynomial function of the atomic number. Based on these findings, we developed a fitting formula to calculate the number buildup factor using the input variables of sample thickness, mass density, and atomic number. The accuracy of the fitting formula was evaluated by comparing its results with number buildup factor values computed by MCNP6 code. The comparison showed relative deviations below 1% for all the investigated cases, demonstrating the high accuracy and reliability of the fitting formula.
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Huynh Dinh Chuong, Le Thi Ngoc Trang, Hoang Duc Tam, Vo Hoang Nguyen, Tran Thien Thanh
NDT & E International Available online 4 May 2020, 102281
