MCNP simulation of the dose distribution in liver cancer treatment for BNC therapy

Krstić, Dragana; Jovanović, Z; Markovic, V.M.; Nikezić, D.; Urosevic, V.

doi:10.2478/s11534-014-0507-2

Cited by 6 publications

(4 citation statements)

References 13 publications

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“…This study simulates Thyroid cancer with Male ORNL MIRD phantom and uses I-131 radioactive which are distributed with MCNPX program. (Monte Carlo Team, 2000;Cecen, 2013;Krstic, 2014;Agita, 2011). .…”

Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation in Internal Radiotherapy of Thyroid Cancer

Oktajianto

Setiawati

2020

Int. J. Eng. Tech. Mgmt. Res.

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Thyroid radiotherapy is a cancer therapy that is treated by giving radioactive I-131 in Thyroid gland. This cancer is at the ninth from ten of common malignant cancer. A man has higher risk to get Thyroid cancer than a woman has. This organ is lain near human neck. This research aim was to simulate particle track of radiation I-131 and determine an absorbed dose and effective dose in Thyroid and other organs around Thyroid such as Brain, Lung and Cervical vertebrae. The simulation and calculation used Monte Carlo method operated by MCNPX software. Geometry of Thyroid and other organs used ORNL MIRD phantom geometry. From the results, it shown that particle track of radiation was distributed at Thyroid while several particles radiated other organs. The absorbed dose in Thyroid and other organs increased every rising activity of I-131 used, but the absorbed dose in other organs was less than in Thyroid. Radiation effect for damage cancer in Thyroid was shown by an effective dose which it increased every rising activity of I-131 used and the maximum effective dose was at 200 mCi activity of I-131. Although the effective dose in Thyroid increased, the effective dose in other organs like Brain, Lung and Cervical vertebrae was still less than in Thyroid so that the use of I-131 each activity did not really influence other organs around Thyroid.

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Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation in Internal Radiotherapy of Thyroid Cancer

Oktajianto

Setiawati

2020

Int. J. Eng. Tech. Mgmt. Res.

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“…The BNCT is said to be very well used in treat ments of can cers in cer tain or gans such as lungs, liver and the brain it self. The MCNP5/X code and ORNL phan tom were used to sim u late the neu tron trans port from the source to the can cer and the tar get or gans [21][22][23].…”

Section: Ma Te Ri Als and Methodsmentioning

confidence: 99%

Dose assessment with MCNP5/X code for boron neutron capture therapy of pancreas cancer

et al. 2021

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Boron neutron capture therapy is based on neutron capture by 10B and creation of high energy alpha particle and recoiled 7Li ion which have ranges comparable to cell dimensions. The MCNP5/X code is applied for calculation of the absorbed doses as well as dose distribution by depth in pancreas cancer and the organs of the analytical and voxelized Oak Ridge National Laboratory phantom, which represents the human body. The depth dose distributions for thermal, epithermal neutrons, and neutron spectrum, show that the absorbed doses are the largest exactly in the cancer, in all cases. It is found by this simulation that the epithermal neutrons are the optimal choice for BNC therapy. They deliver a similar dose to cancer as the thermal neutrons but, spare the healthy tissue more than the thermal ones.

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“…In order to have a neutron capture reaction with a B-10 nucleus, a neutron source in accordance with International Atomic Energy Agency (IAEA) standards is required. There are two types of neutrons that can be used as a neutron source in BNCT, namely thermal neutrons and epitermal neutrons (Krstic et al 2014a). Thermal neutrons are commonly used for cancer cells located on the surface of the skin (superficial).…”

Section: Introductionmentioning

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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MCNP simulation of the dose distribution in liver cancer treatment for BNC therapy

Cited by 6 publications

References 13 publications

Monte Carlo Simulation in Internal Radiotherapy of Thyroid Cancer

Monte Carlo Simulation in Internal Radiotherapy of Thyroid Cancer

Dose assessment with MCNP5/X code for boron neutron capture therapy of pancreas cancer

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

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