استخدم 9Be(p,n)9 B في مسرع الـسيكلترون 9 السوري لحساب كثافة النترونات و الفوتونات الناتجة عن هذا التفاعل كتابع لسماكة هدف Be البيريليوم.
استخدمت بروتونات مسرعة لطاقة 0MeV.15 ، و تيار شدته 0µA.200 .و درس أيضاً التوزع الـزاوي
9)n,p(9Be للنترونات الصادرة عن التفاعل B كتابع لسماكة الهدف، إذْ لوحظ أن القيمة العظمى للكثافـة
9B)n,p(9Be النترونية و الفوتونية تقع عند الزاوية صفر. قورنت القيم الحسابية بالنسبة إلى التفـاعلين
و (n,p(Pb بالقيم التجربية بالنسبة إلى الطيف النترونات الصادر عن هذين التفاعلين، و وجد تطـابق 207
جيد بين القيم الحسابية و التجريبية.
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 energy 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.
References used
htt://www.springeronline.com/series/5267. Access 1/8/2012 At 11.36 AM
http://homepage.univie.ac.at/manfred.drosg/drosg99.pdf. Access 1/8/2012 at 10.05 AM
Thomas E, Blue C, Jacquelyn C. Yanch. (2003). Accelerator-based epithermal neutron sources for boron neutron capture therapy of brain tumors. Journal of Neuro - Oncology 62: 19–31
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.
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
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.
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
The codes (EGSnrc, BEAMnrc) are used to simulate 6MV photon beam produced by
Varian ix linear accelerator and different field size (2020, 1010, 44cm2). The
simulation data is stored in a phase space file that contains complete details of the dat