|
|
|
| Effects of grid methods on precision and efficiency of specific absorbed fraction calculation in Monte Carlo simulation |
| ZHANG Weiyuan, ZHUO Weihai, CHEN Bo, JI Huajun |
| Institute of Radiation Medicine, Fudan University, Shanghai 200032 China |
|
|
|
|
Abstract Objective To compare the precision and efficiency of computing the specific absorbed fraction (SAF) of a reference human with two grid methods in MCNP6.0. Methods Based on the adult female reference voxel phantom provided by the International Commission on Radiological Protection, assuming the liver as the source organ emitting single-energy photons (0.5 MeV), the SAF of each target organ/tissue was calculated by using the mesh method and repeated structure lattice method with the F4, F6, and *F8 tally cards in MCNP6.0. We compared the methods by assessing the relative deviation of SAF and computing time for 27 organs/tissues. Results Compared with reported data, the absolute values of relative deviations of SAF values for all the organs/tissues were less than 5%, except for the eye lens and skin. By using the repeated structure lattice-based *F8 tally, the relative deviations of SAF values of the organs/tissues were all smallest, but with the longest computing time. The computing time of the mesh-based F4 tally was slightly longer than that of the repeated structure lattice-based F6 tally, which was shortest.Conclusion The *F8 tally simultaneously simulating primary and secondary particle transport showed the highest precision. The mesh tally requireda longer computing time than the lattice tally when using the same tally card.
|
|
Received: 26 March 2022
|
|
|
|
|
|
[1] Bolch WE, Eckerman KF, Sgouros G, et al. MIRD Pamphlet No. 21: a generalized schema for radiopharmaceutical dosimetry-standardization of nomenclature[J]. J Nucl Med, 2009, 50(3): 477-484. DOI: 10.2967/jnumed.108.056036
[2] Abrefah RG, Essel PAA, Odoi HC. Estimation of the dose rate of nuclear fuel of Ghana Research Reactor-1 (GHARR-1) using ORIGEN-S and MCNP 6[J]. Progress Nucl Energy, 2018, 105: 309-317. DOI: 10.1016/j.pnucene.2018.02.002
[3] 梅雪松, 张慧, 马玉刚, 等. 用Monte Carlo模拟法和理论计算法研究125I粒子源的剂量分布[J]. 中国辐射卫生, 2011, 20(2): 151-153. DOI: 10.13491/j.cnki.issn.1004-714X.2011.02.013.
Mei XS, Zhang H, Ma YG, et al. Study of dose distribution of 125I seed using Monte Carlo simulation and the theoretical calculation[J]. Chin J Radiol Health, 2011, 20(2): 151-153.
[4] Abo Shdeed T, Nahili M, Abo Issa N, et al. Study of absorbed dose in important organs during helical CT chest scan using MCNP code and MIRD phantom[J]. Egyp J Radiol Nucl Med, 2016, 47(3): 1649-1633. DOI: 10.1016/j.ejrnm.2016.09.004
[5] Leal-Acevedo B, Gamboa-deBuen I. Dose distribution calculation with MCNP code in a research irradiator[J]. Radiat Phys Chem, 2020, 167: 108320. DOI: 10.1016/j.radphyschem.2019.05.010
[6] 洪天祺, 戴瑜. MCNP5计算18F药物诊断的吸收剂量率[J]. 中国辐射卫生,2015,24(2):125-126. DOI: 10.13491/j.cnki.issn.1004-714X.2015.02.010
Hong TQ, Dai Y. Absorbed dose ratecalculation of 18F drug diagnosis with MCNP5[J]. Chin J Radiol Health, 2015, 24(2): 125-126. DOI: 10.13491/j.cnki.issn.1004-714X.2015.02.010
[7] Zubair M, Ahmed E, Hartanto D. Comparison of different glass materials to protect the operators from gamma-rays in the PET using MCNP code[J]. Radiat Phys Chem, 2022, 190: 109818. DOI: 10.1016/j.radphyschem.2021.109818
[8] Van Wijk A,Van den Eynde G, Hoogenboom JE. An easy to implement global variance reduction procedure for MCNP[J]. Ann Nucl Energy, 2011, 38(11): 2496-2503. DOI: 10.1016/j.anucene.2011.07.037
[9] Sweezy J, Brown F, Booth T, et al. Automated variance reduction for MCNP using deterministic methods[J]. Radiat Prot Dosimetry, 2005, 116(1-4): 508-512. DOI: 10.1093/rpd/nci257
[10] Zankl M. Adult male and female reference computational phantoms (ICRP Publication 110)[J]. Jpn J Heal Phys, 2010, 45(4): 357-369. DOI: 10.5453/jhps.45.357
[11] Zankl M, Becker J, Fill U, et al. GSF male and female adult voxel models representing ICRP Reference Man–the present status[C]. The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, 2005, 1721(1).
[12] Valentin J. Basic anatomical and physiological data for use in radiological protection: reference values: ICRP Publication 89[J]. Ann ICRP, 2002, 32(3/4): 1-277. DOI: 10.1016/S0146-6453(03)00002-2
[13] Goorley T, James M, Booth T, et al. Features of MCNP6[J]. Ann Nucl Energy, 2016, 87: 772-783. DOI: 10.1016/j.anucene.2015.02.020
[14] Chauvin Maxime, Borys D, Botta F, et al. Open Dose: Open-Access Resource for Nuclear Medicine Dosimetry[J]. J Nucl Med, 2020, 61(10): 1514-1519. DOI: 10.2967/jnumed.119.240366
[15] Zhang Rui, Fontenot JD, Mirkovic D, et al. Advantages of MCNPX-based lattice tally over mesh tally in high-speed Monte Carlo dose reconstruction for proton radiotherapy[J]. Nucl Technol, 2013, 183(1): 101-106.
|
|
|
|
