SU-E-T-21: A D-D Based Neutron Generator System for Boron Neutron Capture Therapy: A Feasibility Study

2015 ◽  
Vol 42 (6Part12) ◽  
pp. 3335-3335
Author(s):  
M Hsieh ◽  
Y Liu ◽  
L Nie
Keyword(s):  
Feasibility Study ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Neutron Capture Therapy ◽  
Generator System ◽  
Boron Neutron Capture

A feasibility study of a deuterium-deuterium neutron generator-based boron neutron capture therapy system for treatment of brain tumors

2017 ◽  
Vol 44 (2) ◽  
pp. 637-643
Author(s):  
Mindy Hsieh ◽  
Yingzi Liu ◽  
Farshad Mostafaei ◽  
Jean M. Poulson ◽  
Linda H. Nie
Keyword(s):  
Brain Tumors ◽  
Feasibility Study ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture

Feasibility study of SPECT system for online dosimetry imaging in boron neutron capture therapy

2014 ◽  
Vol 88 ◽  
pp. 167-170 ◽  
Author(s):  
B. Hales ◽  
T. Katabuchi ◽  
N. Hayashizaki ◽  
K. Terada ◽  
M. Igashira ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Spect System ◽  
Online Dosimetry

scholarly journals A Design of Boron Neutron Capture Therapy for Cancer Treatment in Indonesia

2016 ◽  
Vol 1 (1) ◽  
pp. 1
Author(s):  
Yohannes Sardjono ◽  
Susilo Widodo ◽  
Irhas Irhas ◽  
Hilmi Tantawy
Keyword(s):  
Neutron Flux ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Epithermal Neutron ◽  
Research Reactor ◽  
Neutron Capture Therapy ◽  
Epithermal Neutron Flux ◽  
Boron Neutron Capture ◽  
Compact Neutron Generator

Boron Neutron Capture Therapy (BNCT) is an advanced form of radiotherapy technique that is potentially superior to all conventional techniques for cancer treatment, as it is targeted at killing individual cancerous cells with minimal damage to surrounding healthy cells. After decades of development, BNCT has reached clinical-trial stages in several countries, mainly for treating challenging cancers such as malignant brain tumors. The Indonesian consortium of BNCT already developed of the design BNCT for many cases of type cancers using many neutron sources. The main objective of the Indonesian consortium BNCT are the development of BNCT technology package which consists of a non nuclear reactor neutron source based on cyclotron and compact neutron generator technique, advanced boron-carrying pharmaceutical, and user-friendly treatment platform with automatic operation and feedback system as well as commercialization of the BNCT though franchised network of BNCT clinics worldwide. The Indonesian consortium BNCT will offering to participate in Boron carrier pharmaceuticals development and testing, development of cyclotron and compact neutron generators and provision of neutrons from the 100 kW Kartini Research Reactor to guide and to validate compact neutron generator development. Studies were carried out to design a collimator which results in epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) at the Kartini Research Reactor by means of Monte Carlo N-Particle 5 (MCNP5) codes. Reactor within 100 kW of output thermal power was used as the neutron source. The design criteria were based on the IAEA’s recommendation. All materials used were varied in size, according to the value of mean free path for each. Monte Carlo simulations indicated that by using 5 cm thick of Ni as collimator wall, 60 cm thick of Al as moderator, 15 cm thick of 60Ni as filter, 1,5 cm thick of Bi as "-ray shielding, 3 cm thick of 6Li2CO3-polyethylene as beam delimiter, with 3-5 cm varied aperture size, epithermal neutron beam with minimum flux of 7,8 x 108 n.cm-2.s-1, maximum fast neutron and "-ray components of, respectively, 1,9 x 10-13 Gy.cm2.n-1 and 1,8 x 10-13 Gy.cm2.n-1, maximum thermal neutron per epithermal neutron ratio of 0,009, and beam minimum directionality of 0,72, could be produced. The beam did not fully pass the IAEA’s criteria, since the epithermal neutron flux was still below the recommended value, 1,0 x 109 n.cm-2.s-1. Nonetheless, it was still usable with epithermal neutron flux exceeded 5 x 108 n.cm-2.s-1. When this collimator was surrounded by 8 cm thick of graphite, the characteristics of the beam became better that it passed all IAEA’s criteria with epithermal neutron flux up to 1,7 x 109 n.cm-2.s-1. it is still feasible for BNCT in vivo experiment and study of many cases cancer type i.e.; liver and lung curcinoma. In this case, thermal neutron produced by model of Collimated Thermal Column Kartini Research Nuclear Reactor, Yogyakarta. Sodium boroncaptate (BSH) was used as in this research. BSH had effected in liver for radiation quality factor as 0.8 in health tissue and 2.5 in cancer tissue. Modelling organ and source used liver organ who contain of cancer tissue and research reactor. Variation of boron concentration was 20, 25, 30, 35, 40, 45, and 47 $g/g cancer. Output of MCNP calculation were neutron scattering dose, gamma ray dose and neutron flux from reactor. Given the advantages of low density owned by lungs, hence BNCT is a solid option that can be utilized to eradicate the cell cancer in lungs. Modelling organ and neutron source for lung carcinoma was used Compact Neutron Generator (CNG) by deuterium-tritium which was used is boronophenylalanine (BPA). The concentration of boron-10 compound was varied in the study; i.e. the variations were 20; 25; 30; 35; 40 and 45 μg.g-1 cancer tissues. Ideally, the primary dose which is solemnly expected to contribute in the therapy is alpha dose, but the secondary dose; i.e. neutron scattering dose, proton dose and gamma dose that are caused due to the interaction of thermal neutron with the spectra of tissue can not be simply omitted. Thus, the desired output of MCNPX; i.e. tally, were thermal and epithermal neutron flux, neutron and photon dose. The liver study variation of boron concentration result dose rate to every variation were0,042; 0,050; 0,058; 0,067; 0,074; 0,082; 0,085 Gy/sec. Irradiation time who need to every concentration were 1194,687 sec (19 min 54 sec);999,645 sec (16 min 39 sec); 858,746 sec (14 min 19 sec); 743,810 sec (12 min 24 sec); 675,156 sec (11 min 15 sec); 608,480 sec (10 min 8 sec); 585,807sec (9 min 45 sec). The lung carcinoma study variations of boron-10 concentration in tissue resulted in the dose rate of each variables respectively were 0.003145, 0.003657, 0.00359, 0.00385, 0.00438 and 0.00476 Gy.sec-1 . The irradiated time needed for therapy for each variables respectively were 375.34, 357.55, 287.58, 284.95, 237.84 and 219.84 minutes.

Feasibility study on the utilization of boron neutron capture therapy (BNCT) in a rat model of diffuse lung metastases

2009 ◽  
Vol 67 (7-8) ◽  
pp. S332-S335 ◽  
Author(s):  
G.J. Bakeine ◽  
M. Di Salvo ◽  
S. Bortolussi ◽  
S. Stella ◽  
P. Bruschi ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Rat Model ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Lung Metastases ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Diffuse Lung

Engineering Design of a Spallation Reaction-Based Neutron Generator for Boron Neutron Capture Therapy

2006 ◽  
Vol 43 (1) ◽  
pp. 9-19 ◽  
Author(s):  
Yoshihisa TAHARA ◽  
Yasushi ODA ◽  
Takako SHIRAKI ◽  
Takehiko TSUTSUI ◽  
Hitoshi YOKOBORI ◽  
...  
Keyword(s):  
Engineering Design ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Neutron Capture Therapy ◽  
Spallation Reaction ◽  
Boron Neutron Capture

Feasibility Study of Boron Neutron Capture Therapy for Inoperable Liver Cancers

1992 ◽  
pp. 497-500
Author(s):  
D. Chiaraviglio ◽  
A. Zonta ◽  
G. Rescigno ◽  
C. Cuzzoni ◽  
L. Calamita ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Liver Cancers
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