scholarly journals Basic Principle Application and Technology of Boron Neutron Capture Cancer Therapy (BNCT) Utilizing Monte Carlo N Particle 5’S Software (MCNP 5) with Compact Neutron Generator (CNG)

2016 ◽  
Vol 1 (1) ◽  
pp. 20
Author(s):  
Aniti Payudan ◽  
Abdullah Nur Aziz ◽  
Yohannes Sardjono
Keyword(s):  
Cancer Therapy ◽  
Neutron Source ◽  
Basic Principle ◽  
Neutron Generator ◽  
Recoil Proton ◽  
Boron Compound ◽  
Normal Tissues ◽  
Toroidal Plasma ◽  
Boron Neutron Capture ◽  
Compact Neutron Generator

The purpose are to know basic principle, needed component, types of compact neutron generator, plus and minus CNG, identify materials can use as collimator, know physics parameters as input software MCNP 5, knowing step simulation with software MCNP 5, dose in BNCT, knowing boron compound that use in BNCT, getting collimator design for BNCT'S application with source is compact neutron generator and count physics parameter of collimator output and compares it with standard IAEA. Method are reading reference and simulation with MCNP 5. The result are BNCT use high linear energy transfer from alpha and lithium as a result of <sup>10</sup>B(n,α)<sup>7</sup>Li reaction. BNCT method is effective for cancer therapy. It is not dangerous to normal tissues. To work perfectly, BNCT needs neutron, boron (BSH and BPA as boron compound) Indonesia have study turmeric as boron compound, neutron source, collimator and dose. Dose component in BNCT that important are dose of recoil proton, dose of gamma, dose alfa and dose radiation to environmentally. CNG produce neutron with fussion reaction of deuterium-deuterium (2,45 MeV), deuterium-tritium (14 MeV), tritium-tritium(11,31 MeV) can used as neutron source BNCT. Many kinds of CNG are axial, coaxial, toroidal, plasma design, accelerator design, and CNG with diameter 2,5 cm. CNG have more benefit than another neutron source, make CNG compatible as BNCT application. Neutron from CNG need collimator to get neutron as IAEA’s parameter.  Material for collimator are wall and aperture (material: Ni, Pb, Bi), moderator (Al, Al<sub>2</sub>O<sub>3, </sub>S, AlF<sub>3</sub>), filter (<sup>6</sup>Li,<sup>10</sup>B, LiF, Al, Cd-nat,<sup>  </sup>Ni-60, BiF<sub>3</sub>, <sup>157</sup>Gd, <sup>151</sup>Eu), gamma shield (Bi, Pb). Simulation using MCNP 5 has severally steps, the first is sketching problem, the second is making listing program with notepad, the third open program on visual editor, and the last is running program. Acquired result is design tube collimator with radius 71 cm and high 139, 5 cm. Design contained on lead wall as thick as 19, 5 cm; moderate: heavy water as thick as 4 cm, AlF<sub>3 </sub>girdle a half of part CNG, MgF <sub>2 </sub>(19 cm + 10 cm), Al (6,5 cm + 5 cm);Gamma shield: bismuth, and aperture with diameter 6 cm by steps aside nickel. The result collimator output cross three of five IAEA'S defaults. They are the ratio among dosed gamma with flux epithermal is 5,738×10 <sup>-24</sup>Gy. cm <sup>2 </sup>.n <sup>-</sup>1, the value of ratio among thermal's neutron flux with epithermal neutron is 0, 02567, and ratio among current with flux neutron completely is 1, 2. Need considerable effort of all part to realize BNCT in Indonesia.

scholarly journals A Design of Boron Neutron Capture Therapy for Cancer Treatment in Indonesia

2016 ◽  
Vol 1 (1) ◽  
pp. 1
Author(s):  
Yohannes Sardjono ◽  
Susilo Widodo ◽  
Irhas Irhas ◽  
Hilmi Tantawy
Keyword(s):  
Neutron Flux ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Epithermal Neutron ◽  
Research Reactor ◽  
Neutron Capture Therapy ◽  
Epithermal Neutron Flux ◽  
Boron Neutron Capture ◽  
Compact Neutron Generator

Boron Neutron Capture Therapy (BNCT) is an advanced form of radiotherapy technique that is potentially superior to all conventional techniques for cancer treatment, as it is targeted at killing individual cancerous cells with minimal damage to surrounding healthy cells. After decades of development, BNCT has reached clinical-trial stages in several countries, mainly for treating challenging cancers such as malignant brain tumors. The Indonesian consortium of BNCT already developed of the design BNCT for many cases of type cancers using many neutron sources. The main objective of the Indonesian consortium BNCT are the development of BNCT technology package which consists of a non nuclear reactor neutron source based on cyclotron and compact neutron generator technique, advanced boron-carrying pharmaceutical, and user-friendly treatment platform with automatic operation and feedback system as well as commercialization of the BNCT though franchised network of BNCT clinics worldwide. The Indonesian consortium BNCT will offering to participate in Boron carrier pharmaceuticals development and testing, development of cyclotron and compact neutron generators and provision of neutrons from the 100 kW Kartini Research Reactor to guide and to validate compact neutron generator development. Studies were carried out to design a collimator which results in epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) at the Kartini Research Reactor by means of Monte Carlo N-Particle 5 (MCNP5) codes. Reactor within 100 kW of output thermal power was used as the neutron source. The design criteria were based on the IAEA’s recommendation. All materials used were varied in size, according to the value of mean free path for each. Monte Carlo simulations indicated that by using 5 cm thick of Ni as collimator wall, 60 cm thick of Al as moderator, 15 cm thick of 60Ni as filter, 1,5 cm thick of Bi as "-ray shielding, 3 cm thick of 6Li2CO3-polyethylene as beam delimiter, with 3-5 cm varied aperture size, epithermal neutron beam with minimum flux of 7,8 x 108 n.cm-2.s-1, maximum fast neutron and "-ray components of, respectively, 1,9 x 10-13 Gy.cm2.n-1 and 1,8 x 10-13 Gy.cm2.n-1, maximum thermal neutron per epithermal neutron ratio of 0,009, and beam minimum directionality of 0,72, could be produced. The beam did not fully pass the IAEA’s criteria, since the epithermal neutron flux was still below the recommended value, 1,0 x 109 n.cm-2.s-1. Nonetheless, it was still usable with epithermal neutron flux exceeded 5 x 108 n.cm-2.s-1. When this collimator was surrounded by 8 cm thick of graphite, the characteristics of the beam became better that it passed all IAEA’s criteria with epithermal neutron flux up to 1,7 x 109 n.cm-2.s-1. it is still feasible for BNCT in vivo experiment and study of many cases cancer type i.e.; liver and lung curcinoma. In this case, thermal neutron produced by model of Collimated Thermal Column Kartini Research Nuclear Reactor, Yogyakarta. Sodium boroncaptate (BSH) was used as in this research. BSH had effected in liver for radiation quality factor as 0.8 in health tissue and 2.5 in cancer tissue. Modelling organ and source used liver organ who contain of cancer tissue and research reactor. Variation of boron concentration was 20, 25, 30, 35, 40, 45, and 47 $g/g cancer. Output of MCNP calculation were neutron scattering dose, gamma ray dose and neutron flux from reactor. Given the advantages of low density owned by lungs, hence BNCT is a solid option that can be utilized to eradicate the cell cancer in lungs. Modelling organ and neutron source for lung carcinoma was used Compact Neutron Generator (CNG) by deuterium-tritium which was used is boronophenylalanine (BPA). The concentration of boron-10 compound was varied in the study; i.e. the variations were 20; 25; 30; 35; 40 and 45 μg.g-1 cancer tissues. Ideally, the primary dose which is solemnly expected to contribute in the therapy is alpha dose, but the secondary dose; i.e. neutron scattering dose, proton dose and gamma dose that are caused due to the interaction of thermal neutron with the spectra of tissue can not be simply omitted. Thus, the desired output of MCNPX; i.e. tally, were thermal and epithermal neutron flux, neutron and photon dose. The liver study variation of boron concentration result dose rate to every variation were0,042; 0,050; 0,058; 0,067; 0,074; 0,082; 0,085 Gy/sec. Irradiation time who need to every concentration were 1194,687 sec (19 min 54 sec);999,645 sec (16 min 39 sec); 858,746 sec (14 min 19 sec); 743,810 sec (12 min 24 sec); 675,156 sec (11 min 15 sec); 608,480 sec (10 min 8 sec); 585,807sec (9 min 45 sec). The lung carcinoma study variations of boron-10 concentration in tissue resulted in the dose rate of each variables respectively were 0.003145, 0.003657, 0.00359, 0.00385, 0.00438 and 0.00476 Gy.sec-1 . The irradiated time needed for therapy for each variables respectively were 375.34, 357.55, 287.58, 284.95, 237.84 and 219.84 minutes.

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 Boron Neutron Capture Therapy (BNCT) using Compact Neutron generator

2016 ◽  
Vol 1 (2) ◽  
pp. 73
Author(s):  
Anggraeni Dwi Susilowati ◽  
Kusminarto Kusminarto ◽  
Yohannes Sardjono
Keyword(s):  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Simulation Method ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Reaction Ratio ◽  
Beam Output ◽  
Neutron Component ◽  
Compact Neutron Generator

<span>Boron Neutron Capture Therapy (BNCT) must be appropriate with five criteria from IAEA. These criteria in order to prevent neutron beam output harm the patient. It can be by using Collimator of neutron source Compact Neutron Generator (CNG) and Monte Carlo simulation method with N particles 5 .CNG is developed by deuteriumtritium reaction (DT) and deuterium-deuterium (DD) reaction. The manufacture result of the collimator is obtained </span><span>epithermal neutron flux value of 1.69e-9 n/cm^2s  for D-T reaction and 8e6 n/cm^2s for D-D reaction, ratio of epithermal and thermal is 1.95e-13 Gy cm^2/n for D-T reaction and for D-D reaction, ratio of fast neutron component is 1.69e-13 Gy cm^2/n for D-T reaction and for D-D reaction, ratio of gamma component is 1.18e-13 Gy cm^2/nfor D-T reaction and for D-D reaction. The Latest </span><span>reaction is current ratio 0.649 for D-T reaction and 0.46 for D-D reaction.</span>

scholarly journals OPTIMIZATION OF COLLIMATOR NEUTRON DESIGN FOR BORON NEUTRON-CAPTURE CANCER THERAPY (BNCT) BASED CYCLOTRON 30 MeV

2017 ◽  
Vol 2 (3) ◽  
pp. 128 ◽  
Author(s):  
Aniti Payudan ◽  
Aris Haryadi ◽  
Farzand Abdullatif
Keyword(s):  
Cancer Therapy ◽  
Cancer Treatment ◽  
Neutron Beam ◽  
Heavy Water ◽  
Neutron Capture ◽  
Neutron Generator ◽  
Independent Variables ◽  
Boron Neutron Capture ◽  
Cylindrical Target ◽  
Water Moderator

<span>This research in BNCT has a goal to design a collimator that can be used for cancer therapy. Simulations were carried out by MCNPX software. A collimator is designed by cyclotron 30 MeV as a neutron generator. Independent variables varied were material and thickness of each collimator’s component to get five of IAEA’s standard of the neutron beam. The result is two collimator designs that can pass all IAEA’s standard. Those designs are cyclotron collimator I and cyclotron collimator II. Collimator designs obtained are tube collimator consisting of a cylindrical target </span><sup>7</sup><span>Be length of 1.4 cm and radius 1 cm, a lead wall with thickness 23 cm, cylindrical heavy water moderator (D</span><sub>2</sub><span>O) with radius 3 cm. Filter Cd-nat for cyclotron collimator I with a thickness of 1 mm and a radius 3 cm. Cyclotron collimator II uses </span><sup>60</sup><span>Ni with a thickness of 5 cm as a filter. The radius aperture is 3 cm. These two collimator designs can be used for cancer treatment with BNCT. Dosimetry calculation and manufacture of prototypes are needed to test the application of this design.</span>

scholarly journals The First Test of the New Neutron Generator at the Všb / Technical University of Ostrava První Test Nového Neutronového Generátoru Na Všb-Tu Ostrava

2013 ◽  
Vol 59 (3) ◽  
pp. 1-5
Author(s):  
Petr Alexa ◽  
Radim Uhlář
Keyword(s):  
Neutron Activation Analysis ◽  
Activation Analysis ◽  
Neutron Activation ◽  
Fast Neutron ◽  
Neutron Source ◽  
Neutron Beam ◽  
Neutron Generator ◽  
Fast Neutron Activation Analysis ◽  
Technical University ◽  
Compact Neutron Generator

Abstract The compact neutron generator MP320 (Thermo Scientific Inc.) operating on the principle of a deuterium-tritium reaction was tested before its planned application as the neutron source for the purpose of Fast Neutron Activation Analysis applications. Plates made from Al, Fe, Sn and Si were irradiated by a 14 MeV neutron beam and typical neutron induced reactions were identified.

Feasibility study of axial compact neutron generator as SAMOP neutron source

2021 ◽  
Author(s):  
Djoko Slamet Pudjorahardjo ◽  
Syarip ◽  
Puradwi Ismu Wahyono
Keyword(s):  
Neutron Source ◽  
Feasibility Study ◽  
Neutron Generator ◽  
Compact Neutron Generator

scholarly journals Detail Engineering Design of Compact Neutron Generator to Support BNCT Facility in Indonesia

2018 ◽  
Vol 3 (1) ◽  
pp. 15-20
Author(s):  
Widarto Widarto
Keyword(s):  
Cancer Therapy ◽  
Engineering Design ◽  
Neutron Generator ◽  
Nuclear Reactors ◽  
Neutron Radiation ◽  
Recoil Nucleus ◽  
Good Choice ◽  
Fast Neutrons ◽  
Epithermal Neutrons ◽  
Compact Neutron Generator

Boron Neutron Capture Therapy (BNCT) is a method of cancer therapy based on neutron radiation which has advantages over the other cancer therapy methods. It uses a stable isotope of 10B which will be an excited isotope of 11B when irradiated by thermal neutron. It immediately (in 10-12 s) breaks into α particle and a lithium recoil nucleus. The two secondary particles play important roles in killing cancer cells. They have a short range in tissue (5 µm and 9 µm respectively) which is less than the average dimension of a cell. This leads to the damage of cancer cell only but the normal cells remain safe. Thermal and epithermal neutrons play important roles in BNCT. From the beginning the neutron sources for BNCT are nuclear reactors which produce high intensity of thermal neutrons (En <0.5 eV), epithermal neutrons (0.5 eV< En < 10 keV) and fast neutrons (En > 10 keV). However, nuclear reactors are very expensive and too large to be used in hospitals. In addition, the operation of nuclear reactors is under restricted protocols related to safety and physical protection. A compact neutron generator is a good choice of neutron source for BNCT. The advantages of compact neutron generator are that the size is small and that the neutron yield is more than 109 ns-1 which satisfies the requirement recommended by IAEA. Additionally, the neutron energy is not so high that it requires a complicated neutron collimator, the operation is easy, and the public acceptance is higher than with nuclear reactors. Based on the requirements of epithermal neutron beam for BNCT facility, the detailed engineering design of compact neutron generator has been made.

scholarly journals Compact neutron generator as external neutron source of subcritical assembly for Mo-99 production (SAMOP)

2020 ◽  
Author(s):  
Djoko Slamet Pudjorahardjo ◽  
Puradwi Ismu Wahyono ◽  
Syarip
Keyword(s):  
Neutron Source ◽  
Neutron Generator ◽  
Compact Neutron Generator

Expanding the Biotherapeutics Realm via miR-34a: “Potent Clever Little” Agent in Breast Cancer Therapy

2019 ◽  
Vol 20 (8) ◽  
pp. 665-673 ◽  
Author(s):  
Mohsen Mohammady ◽  
Seyed I. Ghetmiri ◽  
Mahtab Baharizade ◽  
Mohammad H. Morowvat ◽  
Susan Torabi
Keyword(s):  
Breast Cancer ◽  
Cancer Therapy ◽  
Tumor Suppressor ◽  
Transforming Growth Factor Beta ◽  
Transforming Growth Factor ◽  
Signal Pathways ◽  
Breast Cancer Therapy ◽  
Female Population ◽  
Therapeutic Goals ◽  
Normal Tissues

Background:One of the most prevalent cancers befell to women is considered to be breast cancer (BC). It is also the deadliest among the female population after lung cancer. Additionally, several studies have demonstrated that there is an association between microRNA34-a and breast cancer.Method:We searched PubMed, Web of Science, and Google Scholar up to December 2018. Those studies which have been studied miR-34a and its tumor-suppressing capabilities were considered as the most important topics. Moreover, we extracted articles which were solely focused on microRNA-34a in breast cancer therapy. Finally, 80 articles were included.Results:In comparison with the normal tissues, down-regulation of miR-34a expression is shown considerably in tumor cells. Overexpression of miR-34a acts as a tumor suppressor by transcriptional regulating one of the signaling pathways (TP53), NOTCH, and transforming growth factor beta (TGF-β), Bcl- 2 and SIRT1genes, HDAC1 and HDAC7, Fra-1, TPD52, TLR Via CXCL10. Moreover, drug resistance declines which lead to the apoptosis, cell cycle arrest and senescence. As a result, the proliferation, invasion and metastasis of the tumor are suppressed. The Mrx34 drug contains miR-34a mimic and a lipid vector. MiR-34a as the active ingredient portrays the role of a tumor suppressor. This drug has recently entered the clinical trials studies.Conclusion:These findings suggest a robust cause for developing miR-34a as a therapeutic agent to target BC. In that scenario, miR-34a is strongly useful to introduce new therapeutic goals for BC. Moreover, this review aims to confirm the signal pathways, therapeutic and diagnostic values of miR- 34a in BC and beyond.

scholarly journals LUE-200 Accelerator—A Photo-neutron Generator For The Pulsed Neutron Source “IREN”

2020 ◽  
Vol 15 (11) ◽  
pp. T11006-T11006
Author(s):  
A. Sumbaev ◽  
V. Kobets ◽  
V. Shvetsov ◽  
N. Dikansky ◽  
P. Logatchov
Keyword(s):  
Neutron Source ◽  
Neutron Generator ◽  
Pulsed Neutron ◽  
Pulsed Neutron Source
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