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

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)

Indonesian Journal of Physics and Nuclear Applications ◽

10.24246/ijpna.v1i1.20-33 ◽

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 10B(n,α)7Li 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, Al2O3, S, AlF3), filter (6Li,10B, LiF, Al, Cd-nat, Ni-60, BiF3, 157Gd, 151Eu), 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, AlF3 girdle a half of part CNG, MgF 2 (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 -24Gy. cm 2 .n -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.

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

GeoScience Engineering ◽

10.2478/gse-2014-0054 ◽

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.

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Feasibility study of axial compact neutron generator as SAMOP neutron source

10.1063/5.0066258 ◽

2021 ◽

Author(s):

Djoko Slamet Pudjorahardjo ◽

Syarip ◽

Puradwi Ismu Wahyono

Keyword(s):

Neutron Source ◽

Feasibility Study ◽

Neutron Generator ◽

Compact Neutron Generator

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

Journal of Instrumentation ◽

10.1088/1748-0221/15/11/t11006 ◽

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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Neutron Generator as a Neutron Source for BNCT

Cancer Neutron Capture Therapy ◽

10.1007/978-1-4757-9567-7_63 ◽

1996 ◽

pp. 445-450

Author(s):

Gad Shani ◽

Lev Tsvang ◽

Semion Rozin ◽

Michael Quastel

Keyword(s):

Neutron Source ◽

Neutron Generator

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The Feasibility Research for Detecting the Nitrogen Content in Sewage with NIPGA Method

Applied Mechanics and Materials ◽

10.4028/www.scientific.net/amm.602-605.2445 ◽

2014 ◽

Vol 602-605 ◽

pp. 2445-2448

Author(s):

Fu Quan Jia ◽

Zhu Jun Tian

Keyword(s):

Nitrogen Content ◽

Neutron Source ◽

Total Nitrogen ◽

Gamma Rays ◽

Neutron Generator ◽

Limit Of Detection ◽

Total Nitrogen Content ◽

Feasibility Research ◽

Type Water

NIPGA technology is used in order to detect the total nitrogen content in sewage quickly. D-D neutron generator is used as the neutron source and BGO detector is used to detect gamma rays of nitrogen. The simulated result of MCNP shows the nitrogen’s limit of detection is 0.2 mg/L and the total nitrogen in V-type water can be detected. So this method can be used to detect the total nitrogen content in sewage quickly.

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

Indonesian Journal of Physics and Nuclear Applications ◽

10.24246/ijpna.v1i1.1-13 ◽

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.

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