Problems in determining the absorbed dose in thermal neutron and gamma ray mixed fields: a tissue-equivalent phantom dosimeter for boron neutron capture therapy (BNCT)

1995 ◽  
Author(s):  
Grazia Gambarini
Keyword(s):  
Thermal Neutron ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Tissue Equivalent ◽  
Tissue Equivalent Phantom ◽  
Mixed Fields

scholarly journals Thermal neutron Relative Biological Effectiveness factors for Boron Neutron Capture Therapy from In Vitro Irradiations

2020 ◽  
Author(s):  
María Pedrosa-Rivera ◽  
Javier Praena ◽  
Ignacio Porras ◽  
Manuel Pedro Sabariego ◽  
Ulli Köster ◽  
...  
Keyword(s):  
Tumor Cell ◽  
Thermal Neutron ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Relative Biological Effectiveness ◽  
Neutron Capture Therapy ◽  
Tumor Cell Lines ◽  
Boron Neutron Capture ◽  
Effectiveness Factors ◽  
Biological Effectiveness

The experimental determination of the relative biological effectiveness of thermal neutron factors is fundamental in Boron Neutron Capture Therapy. Present values have been obtained using mixed beams consisting of both neutrons and photons of various energies. A common weighting factor has been used for both thermal and fast neutron doses, although such an approach has been questioned. At the nuclear reactor of the Institut Laue-Langevin a pure low-energy neutron beam has been used to determine thermal neutron relative biological effectiveness factors. Different tumor cell lines, corresponding to glioblastoma, melanoma, and head and neck squamous cell carcinoma, and non-tumor cell lines (lung fibroblast and embryonic kidney) have been irradiated using an experimental arrangement designed to minimise neutron-induced secondary gamma radiation. Additionally, the cells were irradiated with photons at a medical linear accelerator, providing reference data for comparison with that from neutron irradiation. Survival and proliferation were studied after irradiation, yielding the Relative Biological Effectiveness corresponding to the damage of thermal neutrons for the different tissue types.

An international dosimetry exchange for boron neutron capture therapy, Part I: Absorbed dose measurements

2005 ◽  
Vol 32 (12) ◽  
pp. 3729-3736 ◽  
Author(s):  
P. J. Binns ◽  
K. J. Riley ◽  
O. K. Harling ◽  
W. S. Kiger ◽  
P. M. Munck af Rosenschöld ◽  
...  
Keyword(s):  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Absorbed Dose ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Dose Measurements

TU-FG-BRB-07: GPU-Based Prompt Gamma Ray Imaging From Boron Neutron Capture Therapy

2016 ◽  
Vol 43 (6Part35) ◽  
pp. 3757-3757
Author(s):  
S Kim ◽  
T Suh ◽  
D Yoon ◽  
J Jung ◽  
H Shin ◽  
...  
Keyword(s):  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Gamma Ray ◽  
Prompt Gamma ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Gamma Ray Imaging

scholarly journals Dosimetry of In Vivo Experiment for Lung Cancer Based on Boron Neutron Capture Therapy on Radial Piercing Beam Port Kartini Nuclear Reactor by MCNPX Simulation Method

2018 ◽  
Vol 35 (3) ◽  
pp. 213-216
Author(s):  
Atika Maysaroh ◽  
Kusminarto Kusminarto ◽  
Dwi Satya Palupi ◽  
Yohannes Sardjono
Keyword(s):  
Lung Cancer ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Boron Concentration ◽  
Gamma Ray ◽  
Neutron Capture Therapy ◽  
Thermal Neutrons ◽  
Boron Neutron Capture ◽  
Beam Port

Cancer is one of the leading causes of death globally, with lung cancer being among the most prevalent. Boron Neutron Capture Therapy (BNCT) is a cancer therapy method that uses the interaction between thermal neutrons and boron-10 which produces a decaying boron-11 particle and emits alpha, lithium 7 and gamma particles. A study was carried out to model an in vivo experiment of rat organisms that have lung cancer. Dimensions of a rat’s body were used in Konijnenberg research. Modeling lung cancer type, non-small cell lung cancer, was used in Monte Carlo N Particle-X. Lung cancer was modeled with a spherical geometry consisting of 3 dimensions: PTV, GTV, and CTV. In this case, the neutron source was from the radial piercing beam port of Kartini Reactor, Yogyakarta. The variation of boron concentration was 20, 25, 30, 35, 40, and 40 µg/g cancer. The output of the MCNP calculation was neutron scattering dose, gamma-ray dose and neutron flux from the reactor. A neutron flux was used to calculate the alpha proton and gamma-ray dose from the interaction of tissue material and thermal neutrons. The total dose was calculated from a four-dose component in BNCT. The results showed that the dose rate will increase when the boron concentration is higher, whereas irradiating time will decrease.

scholarly journals GPU-based prompt gamma ray imaging from boron neutron capture therapy

2014 ◽  
Vol 42 (1) ◽  
pp. 165-169 ◽  
Author(s):  
Do-Kun Yoon ◽  
Joo-Young Jung ◽  
Key Jo Hong ◽  
Keum Sil Lee ◽  
Tae Suk Suh
Keyword(s):  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Gamma Ray ◽  
Prompt Gamma ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Gamma Ray Imaging
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