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

Hsieh, M; Liu, Yingzi; Mostafaei, Farshad; Poulson, Jean M.; Nie, Linda H.

doi:10.1002/mp.12051

Cited by 4 publications

(2 citation statements)

References 22 publications

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“…Neutron Generators (NG) are extensively used in the various industrial applications such as neutron radiography [1,2], neutron activation analysis [3][4][5], boron neutron capture therapy [6][7][8], explosive material detection [9,10] and material testing [11].…”

Section: Introductionmentioning

confidence: 99%

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

2021

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In recent years, neutron generators have extensively used as neutron sources and vast efforts have been made to develop high yield neutron generators, so the aspect of radiation shielding during the utilization of neutron generators is unavoidable. In this study, dose distribution around the D-D and D-T neutron generator was calculated by using Monte Carlo simulation. Then an effective shielding was designed and different materials with different thicknesses at distinction distances from the generator were examined. Finally, the organs dose was acquired by using ICRP 110 male phantom with and without shielding at different body position relative to generator tube.The results show that the dose induced by the D-T generator is 500 times greater than the D-D generator and the neutron dose is about 100 times more than gamma dose. The dose is reduced about 20 times by increasing the distance up to 5 m, however, the presence of Borated-Polyethylene with a thickness of 60 cm as most effective shielding reduces the whole-body dose up to 60%. Besides, inserting a layer of Pb to Borated-Polyethylene is effective to attenuate the gamma-rays. The received dose to organs depends on the body direction relative to tube head of neutron generator. In general, the best position of tube placement relative to shielding wall are 90 and 180 degrees for the D-T and D-D generators, respectively, distance between the generator tube head and the phantom is suggested 200 cm and it is recommended that for most dose reduction, the operator stands in the anterior-posterior position relative to generator tube. K: Dosimetry concepts and apparatus; Models and simulations; Radiation damage evaluation methods; Neutron sources

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Section: Introductionmentioning

confidence: 99%

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

2021

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“…It was found that the weighted dose rate of brain tumors at a depth of 6.75 cm was 0.022 Gy(w)/s [21]. In 2017, Hsieh et al, used BSA design based on a DD neutron generator to show that the weighted dose rate of brain tumors at a depth of 3 cm is 0.0196 Gy(w)/s [22]. This study aims to calculate BNCT dosimetry in different of cancer positions and irradiation geometries using the PHITS code.…”

Section: Introductionmentioning

confidence: 99%

Calculation of BNCT Dosimetry for Brain Cancer Based on Kartini Research Reactor Using Phits Code

Ntoy

Sardjono²

2017

Tri Dasa Mega

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CALCULATION OF BNCT DOSIMETRY FOR BRAIN CANCER BASED ON KARTINI RESEARCH REACTOR USING PHITS CODE.Cancer is a dangerous disease caused by the growth of a mass of cells that are unnatural and uncontrollable. Glioblastoma, also called as glioblastoma multiforme (GBM), is one of dangerous brain cancer. The dismal prognosis associated with glioblastoma is attributable not only to its aggressive and infiltrative behavior, but also to its location typically deep in the parenchyma of the brain. In resolving this chalenge, the BNCT method can be a solution. This study aims to calculate BNCT dosimetry in different of cancer positions and irradiation geometries using PHITS code. The results show that the deeper the cancers target at brain the slower the total absorbed dose rate of cancer target. It takes a longer treatment time. Based on the treatment time and total absorbed dose rate of cancer target, the TOP irradiation geometry is an appropriate choice in treating the cancer target in this case. To achieve the histopathological cure of GBM at the primary site, the absorbed dose of brain was calculated to be 1.07 Gy and 1.64 Gy for the LLAT and PA irradiation geometry, respectively. While, for cancer position of 3 cm, 5 cm, 7.15 cm, 9 cm, and 11 cm, the absorbed dose of brain is 0.25 Gy, 0.48 Gy, 0.85 Gy, 1.33 Gy, and 2.01 Gy, respectively. In addition to the stochastic effect, it was found also deterministic effects that may be produced such as cataracts.Keywords: BNCT dosimetry; GBM; brain cancer cases; PHITS; MIRD phantom LLAT dan PA. Sedangkan, untuk posisi kanker 3 cm, 5 cm, 7,15 cm, 9 cm, dan 11 cm,25 Gy, 0,48 Gy, 0,85 Gy, 1,33 Gy,and 2,01 Gy. Selain adanya efek stokastik, ditemukan juga efek deterministik yang mungkin dihasilkan seperti katarak. ABSTRAK PERHITUNGAN DOSIMETRI BNCT PADA KANKER OTAK BERBASIS REAKTOR RISET KARTINI MENGGUNAKAN PROGRAM PHITS. Kanker merupakansalahsatu penyakit berbahaya yang diakibatkan oleh tumbuhnya sekumpulan massa sel-sel yang tidak wajar dan tidak terkendali. Salah satu penyakit kanker otak yang berbahaya adalah Glioblastoma atau yang biasa disebut Glioblastoma Multiforme (GBM). Prognosis suram terkait dengan GBM tidak hanya untuk perilaku agresif dan infiltrasi, tetapi juga terhadaplokasi yang jauh di dalam parenkim otak. Untuk menjawab hal tersebut,

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Sensitivity improvement of a deuterium-deuterium neutron generator based in vivo neutron activation analysis (IVNAA) system

Yue,

Tabbassum,

Jaye

et al. 2024

Phys Eng Sci Med

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

Abstract: Results demonstrated that a DD-based BNCT system could be designed to produce neutron beams that have acceptable in-air and in-phantom characteristics. The parameter values were comparable to those of existing BNCT facilities. Continuing efforts are ongoing to improve the DD neutron yield.

Cited by 4 publications

References 22 publications

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

MCNP Dose evaluation around D-D and D-T neutron generators and shielding design

Calculation of BNCT Dosimetry for Brain Cancer Based on Kartini Research Reactor Using Phits Code

Sensitivity improvement of a deuterium-deuterium neutron generator based in vivo neutron activation analysis (IVNAA) system

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