Determination of Energetic Parameters of the (d,t) Neutron Beam of a Neutron Generator

1985 ◽  
Vol 7 (1) ◽  
pp. 125-136 ◽  
Author(s):  
A. Tsechanski ◽  
G. Shani
2016 ◽  
Vol 747 ◽  
pp. 012007
Author(s):  
B Yu Bogdanovich ◽  
E D Vovchenko ◽  
A V Iliinskiy ◽  
A A Isaev ◽  
К I Kozlovskiy ◽  
...  

2019 ◽  
Vol 52 (5) ◽  
pp. 320-325
Author(s):  
A. A. Lychagin ◽  
L. N. Ulyanenko ◽  
S. N. Koryakin ◽  
M. V. Troshina ◽  
S. E. Ulyanenko

1980 ◽  
Vol 178 (2-3) ◽  
pp. 451-458 ◽  
Author(s):  
Mervi Hyvönen-Dabek ◽  
Päivi Nikkinen-Vilkki

2018 ◽  
Vol 177 ◽  
pp. 02003 ◽  
Author(s):  
Aya Hamdy Hegazy ◽  
V.R. Skoy ◽  
K. Hossny

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.


1981 ◽  
Vol 28 (2) ◽  
pp. 1626-1628 ◽  
Author(s):  
Larry G. Evans ◽  
Jacob I. Trombka ◽  
Jeffrey R. Lapides ◽  
Dal H. Jensen

2019 ◽  
Vol 14 ◽  
pp. 155
Author(s):  
D. Karadimos ◽  
K. Ioannides ◽  
P. Assimakopoulos ◽  
N. Tsagas ◽  
P. Paulopoulos ◽  
...  

The analysis technique applied to the data from the FIC (Fast Induction Chamber) detector at the n_TOF facility is presented here. The measurements took place at the installation of CERN in Geneva. The detector was placed in front of the neutron beam for the determination of the neutron induced fission cross-section of various isotopes of the Th cycle. For the data acquisition, several fADC (flash Analog to Digital Converter) channels were used. This facilitated the detailed off-line analysis of data since all information was stored in the computer. The analysis of the data aimed at the discrimination of fission events. For this end we had to deal with three main issues: (1) The subtraction of the background, (2) the fitting of the pulses and (3) the automation of the process. The analysis pertaining to these issues will be further elucidated here.


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