Reference dosimetry calculations for neutron capture therapy with comparison of analytical and voxel models

被引:124
|
作者
Goorley, JT [1 ]
Kiger, WS
Zamenhof, RG
机构
[1] MIT, Nucl Reactor Lab, Cambridge, MA 02139 USA
[2] Harvard Univ, Sch Med, Beth Israel Deaconess Med Ctr, Dept Radiol, Boston, MA 02115 USA
[3] Harvard Univ, Sch Med, Beth Israel Deaconess Med Ctr, Dept Radiat Oncol, Boston, MA 02115 USA
关键词
D O I
10.1118/1.1428758
中图分类号
R8 [特种医学]; R445 [影像诊断学];
学科分类号
1002 ; 100207 ; 1009 ;
摘要
As clinical trials of Neutron Capture Therapy (NCT) are initiated in the U.S. and other countries, new treatment planning codes are being developed to calculate detailed dose distributions in patient-specific models. The thorough evaluation and comparison of treatment planning codes is a critical step toward the eventual standardization of dosimetry, which, in turn, is an essential element for the rational comparison of clinical results from different institutions. In this paper we report development of a reference suite of computational test problems for NCT dosimetry and discuss common issues encountered in these calculations to facilitate quantitative evaluations and comparisons of NCT treatment planning codes. Specifically, detailed depth-kerma rate curves were calculated using the Monte Carlo radiation transport code MCNP4B for four different representations of the modified Snyder head phantom, an analytic, multishell, ellipsoidal model, and voxel representations of this model with cubic voxel sizes of 16, 8, and 4 mm. Monoenergetic and monodirectional beams of 0.0253 eV, 1, 2, 10, 100, and 1000 keV neutrons, and 0.2, 0.5, 1, 2, 5, and 10 MeV photons were individually simulated to calculate kerma rates to a statistical uncertainty of <1% (1 std. dev.) in the center of the head model. In addition, a "generic" epithermal neutron beam with a broad neutron spectrum, similar to epithermal beams currently used or proposed for NCT clinical trials, was computed for all models. The thermal neutron, fast neutron, and photon kerma. rates calculated with the 4 and 8 mm. voxel models were within 2% and 4%, respectively, of those calculated for the analytical model. The 16 mm voxel model produced unacceptably large discrepancies for all dose components. The effects from different kerma data sets and tissue compositions were evaluated. Updating the kerma data from ICRU 46 to ICRU 63 data produced less than 2% difference in kerma rate profiles. The depth-dose profile data, Monte Carlo code input, kerma factors, and model construction files are available electronically to aid in verifying new and existing NCT treatment planning codes. (C) 2002 American Association of Physicists in Medicine.
引用
收藏
页码:145 / 156
页数:12
相关论文
共 50 条
  • [31] TOWARDS A CHEMICAL DOSIMETRY SYSTEM FOR BORON NEUTRON-CAPTURE THERAPY
    MILJANIC, S
    MILJANIC, D
    KRISTOF, ES
    ILIC, R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 1995, 354 (2-3): : 595 - 597
  • [32] The potential use of polymer gel dosimetry in boron neutron capture therapy
    Farajollahi, AR
    Bonnett, DE
    Tattam, D
    Green, S
    PHYSICS IN MEDICINE AND BIOLOGY, 2000, 45 (04): : N9 - N14
  • [33] Monte Carlo based dosimetry for neutron capture therapy of brain tumors
    Zaidil, Lilia
    Belgaid, Mohamed
    Khelifi, Rachid
    THEORETICAL AND EXPERIMENTAL STUDIES IN NUCLEAR APPLICATIONS AND TECHNOLOGY (TESNAT 2016), 2016, 128
  • [34] Thermoluminescence dosimetry of a thermal neutron field and comparison with Monte Carlo calculations
    Fernandes, AC
    Santos, JP
    Kling, A
    Marques, JG
    Gonçalves, IC
    Carvalho, AF
    Santos, L
    Cardoso, J
    Osvay, M
    RADIATION PROTECTION DOSIMETRY, 2004, 111 (01) : 35 - 39
  • [35] A new analytical formula for neutron capture gamma dose calculations in double-bend mazes in radiation therapy
    Ghiasi, Hosein
    Mesbahi, Asghar
    REPORTS OF PRACTICAL ONCOLOGY AND RADIOTHERAPY, 2012, 17 (04) : 220 - 225
  • [36] Comparison of statistical model calculations for stable isotope neutron capture
    Beard, M.
    Uberseder, E.
    Crowter, R.
    Wiescher, M.
    PHYSICAL REVIEW C, 2014, 90 (03):
  • [37] Mixed field dosimetry of neutron beams for Boron Neutron Capture Therapy at the Massachusetts Institute of Technology
    Rogus, RD
    Harling, OK
    Yanch, JC
    CANCER NEUTRON CAPTURE THERAPY, 1996, : 457 - 466
  • [38] Voxel dosimetry: Comparison of MCNPX and DOSXYZnrc Monte Carlo codes in patient specific phantom calculations
    Hadad, Kamal
    Saeedi-Moghadam, Mahdi
    Zeinali-Rafsanjani, Banafsheh
    TECHNOLOGY AND HEALTH CARE, 2017, 25 (01) : 29 - 35
  • [39] A comparison of radiation dose measured in CT dosimetry phantoms with calculations using EGS4 and voxel-based computational models
    Caon, M
    Bibbo, G
    Pattison, J
    PHYSICS IN MEDICINE AND BIOLOGY, 1997, 42 (01): : 219 - 229
  • [40] Neutron Noise Calculations in Hexagonal Geometry and Comparison with Analytical Solutions
    Hoai Nam Tran
    Demaziere, Christophe
    NUCLEAR SCIENCE AND ENGINEERING, 2013, 175 (03) : 340 - 351