Production of a pulseable fission-like neutron flux using a monoenergetic 14MeV neutron generator and a depleted uranium reflector

2008 ◽  
Vol 588 (3) ◽  
pp. 414-423 ◽  
Author(s):  
D. Koltick ◽  
S. McConchie ◽  
E. Sword
Keyword(s):  
Neutron Flux ◽  
Neutron Generator ◽  
Depleted Uranium ◽  
14Mev Neutron

Non-invasive field measurements of soil water content using a pulsed 14MeV neutron generator

2012 ◽  
Vol 120 ◽  
pp. 130-136 ◽  
Author(s):  
S. Mitra ◽  
L. Wielopolski ◽  
R. Omonode ◽  
J. Novak ◽  
J. Frederick ◽  
...  
Keyword(s):  
Water Content ◽  
Soil Water ◽  
Soil Water Content ◽  
Neutron Generator ◽  
Field Measurements ◽  
Non Invasive ◽  
14Mev Neutron

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.

Neutron flux distribution from a 14 MeV neutron generator

1967 ◽  
Vol 50 (1) ◽  
pp. 141-146 ◽  
Author(s):  
H.F. Priest ◽  
F.C. Burns ◽  
G.L. Priest
Keyword(s):  
Neutron Flux ◽  
Neutron Generator ◽  
Flux Distribution ◽  
Neutron Flux Distribution

High spatial resolution fiber based miniature detector for neutron flux mapping in a subcritical assembly and neutron generator

2017 ◽  
Vol 19 (3-4) ◽  
pp. 169-175 ◽  
Author(s):  
Saroj Bishnoi ◽  
P.S. Sarkar ◽  
Mayank Shukla ◽  
Nirmal Ray ◽  
Tarun Patel ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Spatial Resolution ◽  
Neutron Generator ◽  
High Spatial Resolution ◽  
Flux Mapping

scholarly journals Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5

2018 ◽  
Vol 177 ◽  
pp. 02003 ◽  
Author(s):  
Aya Hamdy Hegazy ◽  
V.R. Skoy ◽  
K. Hossny
Keyword(s):  
Neutron Flux ◽  
Neutron Beam ◽  
Gamma Rays ◽  
Neutron Generator ◽  
Nuclear Research ◽  
Experimental Results ◽  
Fast Neutrons ◽  
Gamma Line ◽  
Total Neutron ◽  
Previous Conclusion

Neutron generators are now used in various fields. They produce only fast neutrons; D-D neutron generator produces 2.45 MeV neutrons and D-T produces 14.1 MeV neutrons. In order to optimize shielding-collimator parameters to achieve higher neutron flux at the investigated sample (The signal) with lower neutron and gamma rays flux at the area of the detectors, design iterations are widely used. This work was applied to ROMASHA setup, TANGRA project, FLNP, Joint Institute for Nuclear Research. The studied parameters were; (1) shielding-collimator material, (2) Distance between the shielding-collimator assembly first plate and center of the neutron beam, and (3) thickness of collimator sheets. MCNP5 was used to simulate ROMASHA setup after it was validated on the experimental results of irradiation of Carbon-12 sample for one hour to detect its 4.44 MeV characteristic gamma line. The ratio between the signal and total neutron flux that enters each detector was calculated and plotted, concluding that the optimum shielding-collimator assembly is Tungsten of 5 cm thickness for each plate, and a distance of 2.3 cm. Also, the ratio between the signal and total gamma rays flux was calculated and plotted for each detector, leading to the previous conclusion but the distance was 1 cm.

A Movable Device of Explosives Detection

2017 ◽  
Author(s):  
Zheng Yan ◽  
Tong Ti ◽  
Jing Shi-wei ◽  
Li Huan-yu ◽  
Liu Xuan ◽  
...  
Keyword(s):  
Organic Compounds ◽  
Neutron Generator ◽  
Silicon Detector ◽  
Particle Method ◽  
Explosives Detection ◽  
Thick Wall ◽  
Space Resolution ◽  
Recognition Ability ◽  
14Mev Neutron ◽  
Detection Of Explosives

This paper introduces a movable detection device for explosives hidden in wall. The device is composed of the 14MeV neutron generator, the silicon detector and Φ76mm×76mm LYSO detector. The γ spectra produced by the inelastic scattering interaction provide the relative counts of C, N, O, which are converted into chemical fractions to distinguish the explosives from the organic compounds. The device using associate particle method reduces the background 200–300 times. The 300g ammonium nitrate and TNT explosive simulated samples placed behind the 15cm-thick and 10cm-thick wall is detected by the device, respectively, when the neutron intensity is 1×107n/s. Compared with other methods, the experimental results show that the device with associate particle method has higher detection space resolution ability and explosives recognition ability. The device can provide the support for the detection of explosives.

Angular Distribution of Neutron Flux around the Tritium Target of 14 MeV Neutron Generator

2012 ◽  
Vol 81 (10) ◽  
pp. 104006 ◽  
Author(s):  
Ranjita Mandal ◽  
Genu Radhu Pansare ◽  
Debashish Sengupta ◽  
Vasant Nageshrao Bhoraskar
Keyword(s):  
Angular Distribution ◽  
Neutron Flux ◽  
Neutron Generator ◽  
Tritium Target

Comparison of experimental and computational neutron spectroscopy at a 14MeV neutron generator facility

2009 ◽  
Vol 78 (5) ◽  
pp. 311-317 ◽  
Author(s):  
Edward Waller ◽  
Tom Cousins ◽  
Marc Desrosiers ◽  
Trevor Jones ◽  
Rob Buhr ◽  
...  
Keyword(s):  
Neutron Generator ◽  
Neutron Spectroscopy ◽  
14Mev Neutron
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