Neutrons absorbed dose rate calculations for interstitial brachytherapy with 252Cf sources

被引：7
|
作者：
Paredes, L.
Azorin, J.
Balcazar, M.
Francois, J. L.
机构：
[1] Inst Nacl Invest Nucl, Ocoyoacac 52750, Mex, Mexico
[2] Univ Autonoma Estado Mex, Fac Med, Toluca 50180, Mex, Mexico
[3] Univ Autonoma Metropolitana Iztapalapa, Dept Fis, Mexico City 09340, DF, Mexico
[4] Univ Nacl Autonoma Mexico, Fac Ingn, Dept Sist Energet, Mexico City 04510, DF, Mexico
来源：
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 2007年 / 580卷 / 01期
关键词：
californium; neutron dosimetry; brachytherapy; Monte Carlo code;
D O I：
10.1016/j.nima.2007.05.239
中图分类号：
TH7 [仪器、仪表];
学科分类号：
0804 ; 080401 ; 081102 ;
摘要：
The AAPM TG-43 protocol was used to evaluate the neutron absorbed dose rate from Cf-252 sources for two tissue substitute materials, five normal tissues and six malignant tumours. Three Cf-252 source models (AT, VariSource and mu Selectron) were simulated using the Monte Carlo MCNPX code in spherical geometry for obtaining the following factors: (a) conversion coefficient of neutron air kerma strength, (b) neutron dose rate constant, (c) neutron radial dose function, (d) geometry function, (e) anisotropy function and (f) neutron absorbed dose rate. For the Cf-252 AT source and a Watt fission spectrum, the calculated reference neutron dose rate in water was D-N(r(0), theta(0)) = 1.916cGy h(-1) mu g(-1). The results for the reference neutron dose rate in normal tissues and malignant tumours show how small variations in their elemental composition produce variations in the neutron absorbed dose rate up to 14.9% and 8.4%, respectively, when water and muscle are the reference medium. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码：582 / 585
页数：4
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