Neutron Generator as a Neutron Source for BNCT

1996 ◽  
pp. 445-450
Author(s):  
Gad Shani ◽  
Lev Tsvang ◽  
Semion Rozin ◽  
Michael Quastel
Keyword(s):  
Neutron Source ◽  
Neutron Generator

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

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

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.

Pulsed thermal neutron source at the fast neutron generator

2009 ◽  
Vol 67 (6) ◽  
pp. 1148-1155 ◽  
Author(s):  
Grzegorz Tracz ◽  
Krzysztof Drozdowicz ◽  
Barbara Gabańska ◽  
Ewa Krynicka
Keyword(s):  
Thermal Neutron ◽  
Fast Neutron ◽  
Neutron Source ◽  
Neutron Generator

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.

Absolute experimental and numerical calibration of the 14 MeV neutron source at the Frascati neutron generator

1996 ◽  
Vol 67 (6) ◽  
pp. 2189-2196 ◽  
Author(s):  
M. Angelone ◽  
M. Pillon ◽  
P. Batistoni ◽  
M. Martini ◽  
M. Martone ◽  
...  
Keyword(s):  
Neutron Source ◽  
Neutron Generator

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.

Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes

2018 ◽  
Author(s):  
Yi Yang ◽  
Yiguo Li ◽  
Bin Zhao
Keyword(s):  
Neutron Source ◽  
Neutron Beam ◽  
Neutron Generator ◽  
Epithermal Neutron ◽  
Beam Quality ◽  
Geometric Model ◽  
Source Model ◽  
Neutron Energy Spectrum ◽  
Compact Structure ◽  
Irradiation Device

Accelerator used for Boron Neutron Capture Therapy (BNCT) is the development trend of cancer treatment in the future. Neutron generator is a neutron source with compact structure, easy to operate, and lower price in accelerator (the structure of neutron tube is more compact). It has a high feasibility of establishing in the hospital when compared with other types of accelerator. At present, the D-D reaction has higher neutron yield than other reactions, more easy to get D material. Therefore, the epithermal neutron beam based on D-D neutron generator is studied for BNCT usage. First, the calculation model is established by MCNP program, including the neutron source model, the geometric model of the irradiation device. The specific neutron energy spectrum and angular distribution of the D-D reaction are theoretically analyzed when establishing the D-D reaction neutron source model. The basic structure models of typical irradiation devices are designed, and then the optimal suitable moderator material for the irradiation device is studied from the neutron reaction cross section, the combination of iron and Fluental materials is optimum. The irradiation device with multi D-D neutron tubes’ combination as BNCT neutron source is designed. It can be concluded by study that the parameters at the beam exit are epithermal neutron flux density 2.01 × 108 n/cm2 · s, fast neutron contamination 1.33 × 10−11 Gy · cm2/n, γ contamination 5.79 × 10−17 Gy · cm2/n, for the combination with 6 neutron tubes. The result can meet IAEA’s requirements for BNCT epithermal neutron beam quality.

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