Dose determination using alanine detectors in a mixed neutron and gamma field for boron neutron capture therapy of liver malignancies

被引:10
作者
Schmitz, Tobias [1 ,2 ]
Blaickner, Matthias [3 ]
Ziegner, Markus [3 ,4 ]
Bassler, Niels [5 ]
Grunewald, Catrin [2 ]
Kratz, Jens V. [1 ]
Schuetz, Christian [1 ]
Langguth, Peter [2 ]
Sharpe, Peter [6 ]
Palmans, Hugo [6 ]
Holzscheiter, Michael H. [7 ,8 ]
Otto, Gerd [9 ]
Hampel, Gabriele [1 ]
机构
[1] Johannes Gutenberg Univ Mainz, Inst Nucl Chem, D-55099 Mainz, Germany
[2] Johannes Gutenberg Univ Mainz, Dept Pharm & Toxicol, D-55099 Mainz, Germany
[3] AIT Austrian Inst Technol GmbH, Vienna, Austria
[4] Vienna Univ Technol, TUWien, A-1040 Vienna, Austria
[5] Aarhus Univ Hosp, Dept Expt Clin Oncol, DK-8000 Aarhus, Denmark
[6] Natl Phys Lab, Teddington TW11 0LW, Middx, England
[7] Univ New Mexico, Dept Phys & Astron, Albuquerque, NM 87131 USA
[8] Max Planck Inst Nucl Phys, D-69117 Heidelberg, Germany
[9] Johannes Gutenberg Univ Mainz, Dept Hepatobiliary Pancreat & Transplantat Surg, D-55099 Mainz, Germany
基金
美国国家科学基金会;
关键词
DOSIMETRY; REACTOR; MAINZ;
D O I
10.3109/0284186X.2011.582516
中图分类号
R73 [肿瘤学];
学科分类号
100214 ;
摘要
Boron Neutron Capture Therapy for liver malignancies is being investigated at the University of Mainz. One important aim is the set-up of a reliable dosimetry system. Alanine dosimeters have previously been applied for dosimetry of mixed radiation fields in antiproton therapy, and may be suitable for measurements in mixed neutron and gamma fields. Material and methods. Two experiments have been carried out in the thermal column of the TRIGA Mark II reactor at the University of Mainz. Alanine dosimeters have been irradiated in a phantom and in liver tissue. Results. For the interpretation and prediction of the dose for each pellet, beside the results of the measurements, calculations with the Monte Carlo code FLUKA are presented here. For the phantom, as well as for the liver tissue, the measured and calculated dose and flux values are in good agreement. Discussion. Alanine dosimeters, in combination with flux measurements and Monte Carlo calculations with FLUKA, suggest that it is possible to establish a system for monitoring the dose in a mixed neutron and gamma field for BNCT and other applications in radiotherapy.
引用
收藏
页码:817 / 822
页数:6
相关论文
共 15 条
[1]  
Battistoni G, 2007, AIP CONF PROC, V896, P31, DOI 10.1063/1.2720455
[2]  
Eberhardt K, 2000, KERNTECHNIK, V65, P269
[3]  
HANSEN JW, 1989, RADIAT PROT DOSIM, V27, P85
[4]   THEORETICAL AND EXPERIMENTAL RADIATION EFFECTIVENESS OF THE FREE-RADICAL DOSIMETER ALANINE TO IRRADIATION WITH HEAVY CHARGED-PARTICLES [J].
HANSEN, JW ;
OLSEN, KJ .
RADIATION RESEARCH, 1985, 104 (01) :15-27
[5]  
HANSEN JW, 1987, RADIAT PROT DOSIM, V19, P43
[6]   Dose response of alanine detectors irradiated with carbon ion beams [J].
Herrmann, Rochus ;
Jaekel, Oliver ;
Palmans, Hugo ;
Sharpe, Peter ;
Bassler, Niels .
MEDICAL PHYSICS, 2011, 38 (04) :1859-1866
[7]  
IAEA, 2001, IAEA-TECDOC-1223
[8]   Bilobar colorectal liver metastases: Treatment options [J].
Jaeck, Daniel ;
Pessaux, Patrick .
SURGICAL ONCOLOGY CLINICS OF NORTH AMERICA, 2008, 17 (03) :553-+
[9]  
JESSKE L, 2002, CHIR GASTRENTEROL, V18, P128
[10]   Dose calculation in biological samples in a mixed neutron-gamma field at the TRIGA reactor of the University of Mainz [J].
Schmitz, Tobias ;
Blaickner, Matthias ;
Schuetz, Christian ;
Wiehl, Norbert ;
Kratz, Jens V. ;
Bassler, Niels ;
Holzscheiter, Michael H. ;
Palmans, Hugo ;
Sharpe, Peter ;
Otto, Gerd ;
Hampel, Gabriele .
ACTA ONCOLOGICA, 2010, 49 (07) :1165-1169