Presenting and simulating an innovative model of liver phantom and applying two methods for dosimetry of it in neutron radiation therapy.

Aim: A new model of liver phantom is defined, then this model is simulated by MCNPX code for dosimetry in neutron radiation therapy. Additionally, an analytical method is applied based on neutrons collisions and mathematical equations to estimate absorbed doses. Finally, the results obtained from two methods are compared to each other to justify the approach.

Measurements of the thermal neutron flux for an accelerator-based photoneutron source.

To have access to an appropriate neutron source is one of the most demanding requirements for neutron studies. This is important specially in laboratory and clinical applications, which need more compact and accessible sources. The most known neutron sources are fission reactors and natural isotopes, but there is an increasing interest for using accelerator based neutron sources because of their advantages.

Differentiation in boron distribution in adult male and female rats' normal brain: a BNCT approach.

Boron distribution in adult male and female rats' normal brain after boron carrier injection (0.005 g Boric Acid+0.005 g Borax+10 ml distilled water, pH: 7.

Effect of time period after boric acid injection on 10B absorption in different regions of adult male rat's brain.

Distribution of (10)B in different regions of rat normal brain was studied. Two groups were chosen as control and trial. Trial group received 2 ml of neutral boron compound.

Design and simulation of a neutron source based on an electron linear accelerator for BNCT of skin melanoma.

The PNS project is devoted to the design and simulation of a Photo-Neutron Source for BNCT using a Varian 2300C/D electron accelerator. This paper describes the production of the high-energy gamma-rays followed by neutron production in (gamma,n) reaction. To optimize the whole setup and maximize the neutron flux, the FLUKA code is employed to simulate the system.

Theoretical and experimental analysis of titanium Compton profile using (137)Cs.

The objective of this study is to measure the Compton profile of a titanium coating on a glass substrate, comparing it with a profile computed by the Hillman and Skilman program based on the Hartree-Fock model. The experimental Compton profile was obtained using 661.7keV gamma-rays from a (1)Ci (137)Cs source and a 3''x3'' NaI(Tl) detector.

Determination of boron distribution in rat's brain, kidney and liver.

To determine relative boron distribution in rat's brain, liver and kidney, a mixture of boric acid and borax, was used. After transcardial injection of the solution, the animals were sacrificed and the brain, kidney and liver were removed. The coronal sections of certain areas of the brain were prepared by freezing microtome.

Monte Carlo assessment of soil moisture effect on high-energy thermal neutron capture gamma-ray by 14N.

Among many conventional techniques, nuclear techniques have shown to be faster, more reliable, and more effective in detecting explosives. In the present work, neutrons from a 5 Ci Am-Be neutron source being in water tank are captured by elements of soil and landmine (TNT), namely (14)N, H, C, and O. The prompt capture gamma-ray spectrum taken by a NaI (Tl) scintillation detector indicates the characteristic photo peaks of the elements in soil and landmine.