Monte Carlo calculations of lung dose in ORNL phantom for boron neutron capture therapy

Krstić, Dragana; Markovic, V.M.; Jovanović, Z; Milenkovic, Biljana; Nikezić, D.; Atanackovic, J.

doi:10.1093/rpd/nct365

Cited by 11 publications

(8 citation statements)

References 10 publications

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“…The phantom material consisted of three tissues, namely the lungs (blue), bone (green), and soft tissue (yellow), as shown in Figure 1 (Krstic et al 2014b). The materials in the phantom were chosen to be as close as possible to the tissues of humans.…”

Section: Patient Modelmentioning

confidence: 99%

Dose Analysis of Boron Neutron Capture Therapy (BNCT) Treatment for Lung Cancer Based on Particle and Heavy Ion Transport Code System (PHITS)

Harish

Warsono

Sardjono

2020

AJSTD

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The objectives of this study were to determine the effect of boron concentration on total dose rate for lung cancer treatment, and to determine the effect of boron concentration on the length of irradiation time for lung cancer treatment. This study was computer simulation-based using the Particle and Heavy Ion Transport code System (PHITS) by defining the geometry and components of lung cancer and the surrounding organism as the object being studied and the source of radiation used. The type of phantom used was the ORNL of an adult Asian male. The neutron source used was Kartini Reactor. The independent variable was the boron concentration of 30, 40, 50, 60, and 70 ?g/g cancer tissue and the dependent variables were the dose rate and the irradiation time. The results of this study indicated that the larger the amount of boron concentration that was injected, the higher the rate of total dose the organ received, where the total dose rate for each variation of boron concentration were 1.34 × 10-3 Gy/s, 1.71 × 10-3 Gy/s, 2.07 × 10-3 Gy/s, 2.42 × 10-3 Gy/s, and 2.78 × 10-3 Gy/s, and the larger the amount of boron concentration that was injected, the faster the irradiation time for the treatment of lung cancer was, where the irradiation time required for each variation of boron concentration was 37294 s, 29240 s, 24180 s, 20633 s, and 17996 s.

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Section: Patient Modelmentioning

confidence: 99%

Dose Analysis of Boron Neutron Capture Therapy (BNCT) Treatment for Lung Cancer Based on Particle and Heavy Ion Transport Code System (PHITS)

Harish

Warsono

Sardjono

2020

AJSTD

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“…The ORNL MIRD phantom has been used for BNCT-related research [28,29]. It was created by researchers at Hanyang University in Korea.…”

Section: Patient Modelmentioning

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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“…->1,0× 10 9 < 2,0 × 10 -13 < 2,0 × 10 -13 > 100 > 20 > 0,7 . The ORNL phantom cross section view (Krstic et al, 2014) tomography imaging and ORNL phantom. The tomography imaging and ORNL phantom crosssection views are shown in Fig.1 and Fig.2, respectively.…”

Section: Iaeamentioning

confidence: 99%

Clinical trial design of Boron Neutron Capture Therapy on breast cancer using D-D coaxial compact neutron generator as neutron source and Monte Carlo N-Particle simulation method

Pasaribu

Kusminarto

Sardjono

2016

ijpna

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A clinical trial simulation of Boron Neutron Capture Therapy (BNCT) for breast cancer was conducted at National Nuclear Energy Agency Yogyakarta, Indonesia. This was motivated by high rate of breast cancer in the world, especially in Indonesia. BNCT is a type of therapy by nuclear reaction 10B(n,α)7Li that produces kinetic energy totaling 2.79 MeV. High Linear Energy Transfer (LET) radiation of α-particle and recoil 7Li would locally deposit their energy in a range of 5-9 μm, which corresponds to the human cell diameter. Fast neutron coming out of Compact Neutron Generator (CNG) was moderated using Fe and MgF2 material. A collimator, along with breast cancer and the corresponding organ at risk were designed compatible to Monte Carlo N-Particle X (MCNPX). The radiation were simulated by the MCNPX software and the physical quantities were counted by tally MCNPX codes. The highest neutron thermal flux was found at a depth of 1.4 cm on fat tissue. En face and upward intersection radiation techniques were adopted for the breast cancer radiation. The average dose rate of radiation used on breast cancer was 1.72×10-5 Gy/s for the en face method and 8.98×10-6 Gy/s for the upward intersection method. Dose 50±3 Gy was given into cancer cell, (4.18±0.06) ×10-2 Gy into heart and (8.16±0.06) ×10-2Gy into lung for 806.34 hours irradiation.

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Monte Carlo calculations of lung dose in ORNL phantom for boron neutron capture therapy

Cited by 11 publications

References 10 publications

Dose Analysis of Boron Neutron Capture Therapy (BNCT) Treatment for Lung Cancer Based on Particle and Heavy Ion Transport Code System (PHITS)

Dose Analysis of Boron Neutron Capture Therapy (BNCT) Treatment for Lung Cancer Based on Particle and Heavy Ion Transport Code System (PHITS)

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

Clinical trial design of Boron Neutron Capture Therapy on breast cancer using D-D coaxial compact neutron generator as neutron source and Monte Carlo N-Particle simulation method

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