scholarly journals Dose Analysis in Boron Neutron-capture Cancer Therapy (BNCT) Neutron Generator Based for Breast Cancer

2019 ◽  
Vol 4 (1) ◽  
pp. 8-11
Author(s):  
Rawi Pramusinta ◽  
Rawi Pramusinta ◽  
R Zailani ◽  
Yohannes Sardjono
Keyword(s):  
Breast Cancer ◽  
Neutron Scattering ◽  
Dose Rate ◽  
Neutron Generator ◽  
Boron Concentration ◽  
Irradiation Time ◽  
Gamma Dose ◽  
Time Interval ◽  
Boron Neutron Capture ◽  
Independent Variable

The purpose of this study is to know the concentration of boron and irradiation times which optimizes the treatment of breast cancer using the BNCT method. This research was conducted by using MCNPX simulation which outputs are flux neutron, neutron scattering dose and gamma dose. The neutron source used is the BSA D-D Neutron generator model. The independent variable of this research is the boron concentration injected into the cancer. The dependent variable is the total dose rate and irradiation time which determines the effectiveness of  BNCT therapy. The controlled variables are the output of the neutron flux, dose and gamma neutron scattering dose. The results showed that in the range of 70-150 µg/g, the dose rate received by cancer increases with increasing the concentration of boron-10. If the dose rate is increased, the irradiation time interval will be faster. The Boron dose of 70 μg/g and the dose rate of irradiation 0.00293603 Gy/sec needs an irradiation time of 409.43 minutes; the boron dose of 90 µg/g and the dose rate of irradiation 0.00241049 Gy/sec needs an irradiation time of 345.71 minutes; the boron dose of 110 µg/g and the dose rate of irradiation 0.00271236 Gy/sec needs an irradiation time of 307.24 minutes; the boron dose of 130 µg/g and the dose rate of irradiation 0.00303389 Gy/sec needs an irradiation time of 274.67 minutes; and the boron dose 150 µg/g and the dose rate of irradiation 0.00334565 Gy/sec needs an irradiation time of 249.08 minutes. The Optimum concentration of boron is 150 µg/g with irradiation time of 249.08 minutes.

Advanced Application of BNCT in Advanced Cancers

2009 ◽  
Author(s):  
Manuel L. Sztejnberg ◽  
Tatjana Jevremovic
Keyword(s):  
Breast Cancer ◽  
Cancer Treatment ◽  
Boron Concentration ◽  
Breast Cancer Treatment ◽  
Breast Cancers ◽  
New Approach ◽  
Tolerance Dose ◽  
Boron Neutron Capture ◽  
Treatment Conditions ◽  
Higher Doses

We present a new concept of one form of radiation binary targeted therapy that may offer hope for the often fatal relapsed and/or metastasized HER2+ cancers. The idea is to deliver boronated (boron-10 isotope) anti-HER2 monoclonal antibodies (mAbs) to the patient to be deposited preferentially into the tumor followed by one session of a low energy neutron irradiation. Based on actual computed tomography data, we present the comprehensive theoretical (numerical) modeling of the new approach in designing the treatment conditions for the boron neutron capture therapy (BNCT) using the MITRII-FCB neutron beam facility. The results show the effectiveness of the proposed treatment option for the advanced breast cancers and the metastasized breast cancers in the lungs of a patient. Our theoretical analysis concludes that with a boron concentration of ∼316 μg/g in tumor and a tumor-to-healthy tissue boron concentration ratio of 35:1, this new BNCT breast cancer treatment can be performed with very low doses to normal tissue and 50 Gy, or higher, doses delivered to the tumor regions. In particular, when applied to the breast cancer treatment, the resulting doses to skin and lung remain under the tolerance dose values. We also went beyond the traditional application of the BNCT and analyzed its applicability in targeting the metastasized breast cancer; using the same theoretical approach we determined the doses delivered into the patient lung with scattered cancer loci.

scholarly journals Monte Carlo assessment of boron neutron capture therapy for the treatment of breast cancer

2005 ◽  
Vol 20 (1) ◽  
pp. 27-32 ◽  
Author(s):  
Daniel Mundy ◽  
Tatjana Jevremovic
Keyword(s):  
Breast Cancer ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Boron Concentration ◽  
Treatment Options ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Thermal Neutron Irradiation ◽  
Starting Point ◽  
Her 2

For a large number of women who are diagnosed with breast cancer every year the avail able treatment options are effective, though physically and mentally taxing. This work is a starting point of a study of the efficacy of boron neutron capture therapy as an alternative treatment for HER-2+ breast tumors. Using HER-2-specific monoclonal anti bodies coupled with a boron-rich oligomeric phosphate diester, it may be possible to deliver sufficient amounts of 10B to a tumor of the breast to al low for selective cell destruction via irradiation by thermal neutrons. A comprehensive computational model (MCNP) for thermal neutron irradiation of the breast is described, as well as the results of calculations made using this model, in order to determine the optimum boron concentration within the tumor for an effective boron neutron capture therapy treatment, as compared with traditional X-ray radiotherapy. The results indicate that a boron concentration of 50-60 mg per gram of tumor tissue is optimal when considering treatment times, dose distributions and skin sparing. How ever these results are based upon best-guess assumptions that must be experimentally verified.

scholarly journals 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

2016 ◽  
Vol 1 (1) ◽  
pp. 34
Author(s):  
Rosenti Pasaribu ◽  
Kusminarto Kusminarto ◽  
Yohannes Sardjono
Keyword(s):  
Breast Cancer ◽  
Clinical Trial ◽  
Monte Carlo ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
En Face ◽  
Compact Neutron Generator

<span>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 </span><sup>10</sup><span>B(n,α)</span><sup>7</sup><span>Li that produces kinetic energy totaling 2.79 MeV. High Linear Energy Transfer (LET) radiation of α-particle and recoil </span><sup>7</sup><span>Li 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 MgF</span><sub>2</sub><span> 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</span><sup>-5 </sup><span>Gy/s for the en face method and 8.98×10</span><sup>-6 </sup><span>Gy/s for the upward intersection method. Dose 50±3 Gy was given into cancer cell, (4.18±0.06) ×10</span><sup>-2</sup><span> Gy into heart and (8.16±0.06) ×10</span><sup>-2</sup><span>Gy into lung for 806.34 hours irradiation.</span>

scholarly journals Desain Beam Shaping Assembly (BSA) berbasis D-D Neutron Generator 2,45 MeV untuk Uji Fasilitas BNCT

2015 ◽  
Vol 5 (02) ◽  
pp. 25 ◽  
Author(s):  
Desman P. Gulo ◽  
Suryasatriya T. ◽  
Slamet Santosa ◽  
Y. Sardjono
Keyword(s):  
Breast Cancer ◽  
Neutron Generator ◽  
Epithermal Neutron ◽  
Beam Shaping ◽  
Neutron Capture Therapy ◽  
Total Production ◽  
Cancer Treatments ◽  
Epithermal Flux ◽  
Boron Neutron Capture ◽  
Beam Shaping Assembly

<p>Boron Neutron Capture Therapy (BNCT) is one of the cancer treatments that are being developed in nowadays. In order to support BNCT treatment for cancer that exists in underneath skin like breast cancer, the facility needs a generator that is able to produce epithermal neutron. One of the generator that is able to produce neutron is D-D neutron generator with 2.45 MeV energy. Based on the calculation of this paper, we found that the total production of neutron per second (neutron yield) from Neutron Generator (NG) by PSTA-BATAN Yogyakarta is 2.55×10<sup>11 </sup>n/s. The energy and flux that we found is in the range of quick neutron. Thus, it needs to be moderated to the level of epithermal neutron which is located in the interval energy of 1 eV to 10 KeV with 10<sup>9</sup> n/cm<sup>2</sup>s flux. This number is the recommendation standard from IAEA. Beam Shaping Assembly (BSA) is needed in order to moderate the quick neutron to the level of epithermal neutron. One part of BSA that has the responsibility in moderating the quick neutron to epithermal neutron is the moderator. The substance of moderator used in this paper is MgF<sub>2</sub> and A1F<sub>3</sub>. The thickness of moderator has been set in in such a way by using MCNPX software in order to fulfill the standard of IAEA. As the result of optimizing BSA moderator, the data obtain epithermal flux with the total number of 4.64×10<sup>8 </sup>n/cm<sup>2</sup>/s for both of moderators with the thickness of moderator up to 15 cm. At the end of this research, the number of epithermal flux does not follow the standard of IAEA. This is because the flux neutron that is being produced by NG is relatively small. In conclusion, the NG from PSTA-BATAN Yogyakarta is not ready to be used for the BNCT treatment facility for the underneath skin cancer like breast cancer.</p>

scholarly journals DOSE ANALYZE OF BORON NEUTRON CAPTURE THERAPY (BNCT) AT SKIN CANCER MELANOMA USING MCNPX WITH NEUTRON SOURCE FROM THERMAL COLUMN OF KARTINI REACTOR

2017 ◽  
Vol 2 (3) ◽  
pp. 111
Author(s):  
Siti Rosidah ◽  
Yohannes Sardjono ◽  
Yosaphat Sumardi
Keyword(s):  
Skin Cancer ◽  
Neutron Flux ◽  
Dose Rate ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Irradiation Time ◽  
Cancer Tissue ◽  
Neutron Capture Therapy ◽  
Radiation Dose Rate ◽  
Boron Neutron Capture

<span>This research aims to determine the amount of radiation dose rate that can be accepted and the irradiation time that is required from Boron Neutron Capture Therapy (BNCT) cancer therapy to treat melanoma skin cancer. This research used the simulation program, MCNPX by defining the geometric dimensions of the tissue component, and describing the radiation source that were used. The outputs obtained from the MCNPX simulation were the neutron flux and the neutron scattering dose that came out from the collimator. The value of neutron flux was used to calculate the dose which comes from the interaction between the neutron and the material in the cancer tissue. Based on the results of the research, the dose rate to treat cancer tissue for boron is 10 μg/g of tumor, which translates to about 0.019241 Gy/second and  requires 25.98 minutes of irradiation time, 15 μg/g of tumor translates to 0.021854 Gy/second and requires 2.,87 minutes, 20 μg/g of tumor translates to 0.022902 Gy/second and requires 21,83 minutes, 25 μg/g of tumor translates to 0.0271275 Gy/second and requires 18.43 minutes, 30 μg/g of tumor translates to 0.0297658 Gy/second and requires 16.79 minutes, and 35 μg/g of tumor translates to 0.0343472 Gy/second and requires 14.55 minutes . The irradiation time needed for cancer tissue is shorter when boron concentration greater at the cancerous tissue.</span>

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

2020 ◽  
Vol 35 (3) ◽  
pp. 187-194
Author(s):  
Ahmad Faisal Harish ◽  
Warsono ◽  
Yohannes Sardjono
Keyword(s):  
Lung Cancer ◽  
Ion Transport ◽  
Cancer Treatment ◽  
Total Dose ◽  
Dose Rate ◽  
Boron Concentration ◽  
Irradiation Time ◽  
Heavy Ion ◽  
Code System ◽  
Transport Code

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.

scholarly journals MODELING THE RADIATION SHIELDING OF BORON NEUTRON CAPTURE THERAPY BASED ON 2.4 MEV D-D NEUTRON GENERATOR FACILITY

2018 ◽  
Vol 20 (1) ◽  
pp. 13
Author(s):  
Muhammad Mu’Alim ◽  
Yohannes Sardjono
Keyword(s):  
Radiation Dose ◽  
Dose Rate ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Neutron Capture Therapy ◽  
Radiation Shield ◽  
Radiation Dose Rate ◽  
Boron Neutron Capture ◽  
Borated Polyethylene

Radiation shield at Boron Neutron Capture Therapy (BNCT) facility based on D-D Neutron Generator 2.4 MeV has been modified with pre-designed beam shaping assembly (BSA). Modeling includes the material and thickness used in the radiation shield. This radiation shield is expected to protect workers from radiation doses rate that is not exceed 20 mSv·year-1 of dose limit values. The selected materials are barite, paraffin, polyethylene and lead. Calculations were performed using the MCNPX program with tally F4 to determine the dose rate coming out of the radiation shield not exceeding the radiation dose rate of 10 μSv·hr-1. Design 3 was chosen as the recommended model of the four models that have been made. The 3rd shield design uses a 100 cm thickness of barite concrete as primamary layer to surrounding 100 cm x 100 cm x 166.4 cm room, and a 40 cm borated polyethylene surrounding the barite concrete material. Then 10 cm barite concrete and 10 cm of borated polyethylene are added to reduce the primary radiation straight from the BSA after leaving the main layer. The largest dose rate was 4.58 μSv·h-1 on cell 227 and average radiation dose rate 0.65 μSv·hr-1. The dose rates are lower than the lethal dose that is allowed by BAPETEN for radiation worker lethal dose.Keywords: Radiation shield, tally, radiation dose rate, BSA, BNCT PEMODELAN PERISAI RADIASI PADA FASILITAS BORON NEUTRON CAPTURE THERAPY BERBASIS GENERATOR NEUTRON D-D 2,4 MeV. Telah dimodelkan perisai radiasi pada fasilitas Boron Neutron Capture Therapy (BNCT) berbasis reaksi D-D pada Neutron Generator 2,4 MeV dengan Beam Shaping Assembly (BSA) yang telah didesain sebelumnya. Pemodelan ini dilakukan untuk memperoleh suatu desain perisai radiasi untuk fasilitas BNCT berbasis generator neutron 2,4 MeV. Pemodelan dilakukan dengan cara memvariasikan bahan dan ketebalan perisasi radiasi. Bahan yang dipilih adalah beton barit, parafin, polietilen terborasi dan timbal. Perhitungan dilakukan menggunakan program MCNPX dengan tally F4 untuk menentukan laju dosis yang keluar dari perisai radiasi. Desain periasi radiasi dinyatakan optimal jika radiasi yang dihasilkan diluar perisai radiasi tidak melebihi Nilai Batas Dosis (NBD) yang telah ditentukan oleh BAPETEN. Hasilnya, diperoleh suatu desain perisai radiasi menggunakan lapisan utama beton barit setebal 100 cm yang mengelilingi ruangan 100 cm x 100 cm x 166,4 cm dan polietilen terborasi 40 cm yang mengelilingi bahan beton barit. Kemudian ditambahkan beton barit 10 cm dan polietilen terborasi 10 cm untuk mengurangi radiasi primer yang lurus dari BSA setelah keluar dari lapisan utama. Laju dosis terbesar adalah 4,58 μSv·jam-1 pada sel 227 dan laju dosis rata-rata yang dihasilkan adalah sebesar 0,65 µSv·jam-1. Nilai laju dosis tersebut masih dibawah ambang batas NBD yang diperbolehkan oleh BAPETEN untuk pekerja radiasi.Kata kunci: Perisai radiasi, tally, laju dosis radiasi, BSA, BNCT

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