تصميم حزمة نترونية حرارية عن طريق التفاعل 9Be(p,n)9B لاستعمالها في التصوير النتروني المسرع باستعمال الكوداتMCNP5-BETA و MCNPX

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. Protons with 15.0 MeV, current 200.0 µA and Be target (0.50 cm thickness and 1.0 cm diameter) were used to produce the neutron intensity from the order of 7.864 х 1012 n/s. The calculated value of the thermal neutron flux at the main collimator exit of neutrons is 1.09 х 105 n/cm2 .s for L/D = 110.0 (where: L is the length of the neutrons collimator and D is the diameter of the neutronic aperture). In addition, the calculated values of the content of the neutronic beam from thermal neutron flux and the ratio of the thermal neutron flux to gamma dose at the beam exit are 90.0 % and Фthermal/gamma dose = 1.60 х 108 neutron/mRem, respectively. In this design the neutronic and gamma filters were not used, which reduces the economic cost to build this beam.