Subscribe to the gold package and get unlimited access to Shamra Academy
Register a new userThermal neutron beam design based on9Be(p,n)9B reaction for neutron radiography using MCNPX and MCNP5-BETA codes
تصميم حزمة نترونية حرارية عن طريق التفاعل 9Be(p,n)9B لاستعمالها في التصوير النتروني المسرع باستعمال الكودات MCNP5-BETA و MCNPX
602
1 9
0
(
0
)
Created by
Shamra Editor
Ask ChatGPT about the research
استخدم الكودان MCNP5-BETA و MCNPX 9 لنمذجة التفاعل بروتونات ناتجة باستعمال حزمة Be(p,n)9B عن مسرع السيكلترون السوري، و حسب طيف النترونات الصادر عن هذا التفاعل و أُجريت الحسابات النترونية اللازمة لتصميم حزمة نترونية حرارية لاستخدامها في التصوير بالنترونات الحرارية في المسرع السوري.
The MCNPX and MCNP5-BETA codes were used to simulate the reaction 9Be(p,n)9B in the Syrian cyclotron,to calculate the neutron spectrum emission from this reaction and for neutronic calculations to design of the thermal neutron beam for thermal neutron radiography.
References used
Kaushal, K. M. 2005. Development of a Thermal Neutron Imaging at the N.C.S.U PULSTAR Reactor.ph.D, North Carolina State University, USA
Thomas, R. C. 2000. Development of Neutron Radioscopy at the SLOWPOKE-2 Facility at RMC for the Inspection of CF188 Flight Control Surfaces.ph.D, Faculty of the Royal Military College of Canada, Canada
Eberhardt, J. E., Rainey, S., Stevens, R. J., Sowerby, B. D., Tickner, J. R. 2005. Fast neutron radiography scanner for detection of contraband in air cargo containers. Appl. Radiat. Isot. 63, 179-188
rate research
Read More
The MCNPX and MCNP5C codes are used to simulate the reaction
9Be(p,n)9B. The photons and neutrons intensities resulting of this reaction are
calculated as a functions of the 9Be target thickness. To calculate this intensity,
the protons with energ
y 15.0MeV and protons current 200.0μA are used. In
addition, the angular distribution of the emitted photons and neutrons from the
reaction 9Be(p,n)9B is calculated as a function of the 9Be target thickness. The
maximum value of the photons and neutrons flux is found to be at angle 00 for
thin targets. The calculated values using MCNPX of the neutrons spectrum
emission from reactions of 9Be(p,n)9B and 207Pb(p,n) is compared to
experimental values. There is a good agreement between them.
The MCNP5-beta code was used to calculate the reaction rate and the neutron energy response matrix of a neutron spectrometry consisting of a Polyethylene sphere with variable diameter and BF3 detector, using point and disk neutron sources, the reacti
on rate and the response matrix of disk neutron source shows higher values than those obtained for point neutron source in addition the response with disk neutron source at the energy range shows a maximum value for sphere of 10 inch diameter where the response with point neutron source stile increasing in this condition .The results obtained in this work for the disk neutron source agreed well with published results.
The analytical relationship that gives the neutron beam flux does
not take into account the probability of decay. In this research, we
concluded the analytical relationship of the probability non decay
of free neutron during the passage of the sam
ple to be analyzed by
NAA. And the conclusion of the analytical relationship to the
probability of non-capture of the free neutron during the its passage
of the sample to be analyzed by NAA in a simpler method than the
previous conclusion. We conducted an application study to
investigate the effect of the probability non decay of free
neutrons, that flowing through sample, On the flux of transient
neutron beam, for neutron beam with various large thickness
samples and for different energies of neutrons. The effect of
probability of neutron decay on neutron beam flux could not be
negligible for all the energies which are bigger than of
thermal.
In this study, a simulation of the MTR-22MW reactor and a study
of standard and mixed fuel combustion using the Codes GETERA
and MCNP5.
The Results of the simulation showed that the operation time of the
reactor in the case of standard fuel is 274 days and if the use of
mixed fuel is 135 days.
This papers reports the investigation of extensions of the group by means of the cyclic group A=<a> of order p, where p is a prime number.
It has been concluded from this work that, all non isomorphic extensions of
the group C(n) by means of the group A ,that correspond to irreducible
representations of the group A , are: - p Z
Log in to be able to interact and post comments
comments
Fetching comments
Sign in to be able to follow your search criteria
