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IJSTR >> Volume 2- Issue 12, December 2013 Edition

International Journal of Scientific & Technology Research  
International Journal of Scientific & Technology Research

Website: http://www.ijstr.org

ISSN 2277-8616

A Comparative Study Of Dose Transmission Factor Of Polythene And Borated Polythene For High Neutron Source Shielding

[Full Text]



David. I. Igwesi, M. Sc., Otobong. S. Thomas, M. Sc.



Keywords: Dose, Transmission Factor, Polythene, Borated Polythene, Neutron Source



ABSTRACT: A comparison of the dose transmission factor for Polythene and Borated Polythene against Am/Be neutron source have been investigated to ensure safe working environment for radiation workers. The Dose transmission factors for the materials were estimated using the Monte-Carlo transport code for incident neutron energies ranging from 0.025eV to 10MeV and the measurements were taken at three different neutron source-detector distances of 50cm, 70cm and 90cm by changing the position of the neutron source while the detector remained at fixed position. This study experimentally demonstrates that, by using suitable shielding material around Am/Be neutron source, the dose transmission factor of borated polythene is small compared to the dose transmission factor of polythene for any given thickness, and that the neutron source-detector distance of 90cm being a position where the Am/Be neutron source is very close to the centre of the water tank was found to be the best position for the neutron source to guarantee the safety of the radiation workers.



[1]. J. E. Martin, “Physics for Radiation Protection”. WILEY-VCH Verlag GmbH & Co. KGaA. Weinheim, 2006.

[2]. J. K. Shultis, and R. E. Faw. “Fundamentals of Nuclear Science and Engineering”, Second Edition. CRC Press, 2002.

[3]. P. Rinard, “Neutron Interactions with Matter. In Passive Nondestructive Assay of Nuclear Materials”, (ed. D. Reilly, N. Ensslin, and H. Smith Jr), Nuclear Regulatory Commission, NUREG/CR-5550. Pp. 357-377, 1991.

[4]. H. Y. Kang, C. J. Park, K. S. Seo, and J. S. Yoon, “Evaluation of Neutron Shielding Effects on Various Materials by Using a Cf-252 Source”. Journal of the Korean Physical Society, Vol. 52, No. 6, pp. 1744-1747, 2008.

[5]. F. J. Allen, and A. T. Futterer. “Neutron Transmission Data. Nucleonics”. 21(8), 120, 1963.

[6]. D. R. Ochbelagh, H. M. Hakimabadb, and R.I. Najafabadi. “The investigation of Am–Be neutron source shield effect used on landmine detection”. Nuclear Instruments and Methods in Physics Research A 577, 756–761, 2007.

[7]. S.C. Gujrathi. and J. M. D’auria. “The Attenuation of Fast Neutrons in Shielding Materials”. Nuclear Instruments and Methods 100, 445-452, 1972.

[8]. C. E. Harrison. “High Density Polythene/Boron containing Composites for Radiation Shielding Applications”. An unpublished PhD Thesis, University of Kentucky, 2008.

[9]. Y. Karni, and E. “Greenspan. Medium density hydrogenous materials for shielding against nuclear radiation”. Proceedings, 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington, Texas USA, Vol 1, pp 43-50, 1994.

[10]. J.F. Briesmeiter. (Ed). “MCNP- A general Monte Carlo N-Particle transport code”, Version 4C. LA-13709-M, Los Alamos National Laboratory, 2000.

[11]. Zheng, Y., Newhauser, W., Fontenot, J., Koch, N. and Mohan, R. (2007). Monte Carlo simulations of stray neutron radiation exposures in proton therapy, Journal of Nuclear Materials 361 289-297.

[12]. Sorenson, J. A. and Phelps, M. E. (1987). Physics in Nuclear Medicine, W. B. Saunders Company, Second Edition.

[13]. Coeck, M., Vermeersch, F. and Vanhavere, F. (2002). Neutron shielding evaluation for a small fuel transport case. Nuclear Instruments and Methods in Physics Research A 476, 273–276.

[14]. R.C. Singleterry, and T. A. Sheila, (2000). Materials for Low-Energy Neutron Radiation Shielding. NASA Langley Technical Report Server.