Calculation of the reaction rate and energy response matrix of a neutron spectrometry consisting of a Polyethylene sphere of variable diameter and BF3 detector using the MCNP5-beta code


Abstract in English

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 reaction 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.

References used

Liu, B. H., Greenberg, D. D., Capala, J., Wheeler, F. J., (1996). An Improved Neutron Collimator for Brain Tumor Irradiations in Clinical Boron Neutron Capture Therapy, Medical Physics, 23, 12, pp. 2051-5060
Tanaka, R., Hunt, J. E., Winans, R. E., Thiyagarajan, P., Sato, S., Takanohashi, T., (2003). Aggregates Structure Analysis of Petroleum Asphaltenes with Small-Angle Neutron Scattering, Energy Fuels, 17, 1, pp. 127-134
Wollan, E. O., Koehler, W. C., (1955). Neutron Diffraction Study of the Magnetic Properties of the Series of Perovskite-Type Com pounds [(1 – x)La, xCa]MnO3, Physical Review, 100, 2, pp. 545-563
Manke, I., Hartnig, C., Grünerbel, M., Kaczerowski, J., Lehnert, W., Kardjilov, N., Hilger, A., Banhart, J., Treimer, W., Strobl, M., (2007). Quasi–insitu Neutron Tomography on Polymer Electrolyte Membrane Fuel Cell Stacks, Applied Physics Letters, 90, 8, pp. 184101-1-3
Hakimabad Miri, H., Rafat, M. L., (2009). Improvement the Uniformity of the Gamma Production Rate Distribution with Depth in a Large Biological Sample for an IVNAA Facility, Nu clear Technology & Radiation Protection, 24, 2, pp. 119-125

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