Affiliation:
1. Malaysia Nuclear Agency
2. Malaysian Nuclear Agency
Abstract
Keywords: Boron carbide, concrete, shielding, neutron, attenuation. Abstract. Boron carbide (B4C) is a ceramic material which is effectively absorb thermal neutron due to wide neutron absorption cross section. In this work, B4C is added into concrete as fine aggregates to test the attenuation properties by getting the attenuation coefficient of the concrete/ B4C. The samples of concrete/ B4C were exposing to the thermal neutron radiation source (241-Americium-Berylium) at the dose rate of 29.08 mR/h. The result show that the attenuation coefficient of the sample with 20wt% B4C is 0.299 cm-1 and the sample without B4C is 0.238 cm-1 and hence, concrete/ B4C is suitable as a shielded for thermal neutron radiation.
Publisher
Trans Tech Publications, Ltd.
Reference6 articles.
1. Anon (1981). U. S Department Of The Interior Water And Power Resources Service. Concrete Manual. Eight Edition. New York. A Wiley-Interscience Publication.
2. A. Abdo, , El-Sayed, Ali, M.A.M. and M.R. Ismail. (2002). Influence of Magnetite and Boron Carbide On Radiation Attenuation Of Cement-fiber/composit, Annals of Nuclear Energy 30: 391-403.
3. A. B. Chilton, J. Shultis, F. Kenneth and E. Richard, (1984). Principles of Radiation Shielding. Englewood Cliffs. New Jersey 07632. Prentice-Hall, Inc.
4. M. Atsuhiko, S. Satoshi, K. Masaharu, S. Akira, H. Junichi, 0. Kentaro, Y. Michinori, N. Takeo, K. Atsushi, M. Kei, S. Shinji, H. Takao, M. Makoto, T. Hiroshi, and I. Shinichi, (2004).
5. A.A. Grossman, R.P. Doerner, S. Luckhardt, R. Seraydarian and A. K Burnham, (1999). Transport Properties of Hydrogen Isotopes In Boron Carbide Structures. Journal of Nuclear.
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