Absolute Measurements for Uranium Verification Content in Radiographic Containers
Keywords:
Radiographic Containers, Uranium VerificationAbstract
Depleted Uranium (DU) is used for its very high density in civilian uses include radiation shielding in medical radiation therapy, industrial radiography equipment, containers used to transport radioactive materials. Absolute measurements have been performed for verification of uranium mass content in gamma radiography by using detector’s model developed with MCNP in nuclear safeguard inspection for these samples. Both the experimental results obtained as well as MCNP results are used to estimate the 238U mass content. The determined and the declared 238U masses values are found in an agreement with accuracy from -1.74 % to 1.80 %.
References
. IAEA, IAEA Safeguards glossary, IAEA/SG/I, Vienna- Austria, 1989.
. IAEA, Decay Data of Transactinium Nuclides, technical report series No. 261, IAEA, Vienna- Austria, 1986.
. IAEA, Handbook of nuclear data committee. INDC(NDS) – 248, Vienna- Austria, 1991.
. M. Makarewiez" Determination of depleted uranium in the environment by gamma- ray spectrometry", IAEA Laboratories, Seibersdorf- Austria, 2001.
. A.A.Hamed, W.A.EL-Gammal and I.Badawy " verification of depleted uranium in non- nuclear use" sith radiation physics conference 27- 30 October, assiut, Egypt, 2002.
. M. Ahmadi, M. Rabbani, P. Mir Ahmadpour, J. Appl. Chem. Res. (JACR) 3, 55 (2009).
. J. Kaneko, M. Katagiri, Y. Ikeda, T. Nishitani, in: Proc. 12 Workshop on Radiation Detectors and Their Uses, KEK, Tsukuba 1998, p. 98-4
. C.M. Salgado , L.E.B. Brandão , R. Schirru , C.M.N.A. Pereira , C.C. Conti " Validation of a NaI(Tl) detector’s model developed with MCNP-X code" Progress in Nuclear Energy 59 (2012) 19e25.
. A. A. Mowlavi, R. Izadi Najafabadi, R. Koohi Faygh "Calculation of Intrinsic Efficiency of NaI(Tl) Detector Using MCNP Code" International Journal of Pure and Applied Physics, Vol.1, No.2 (2005), pp. 129-136.
. I. Akkurta, H.O. Tekinb; and A. Mesbahi " Calculation of Detection Efficiency for the Gamma Detector using MCNPX" the International Conference on Computational and Experimental Science and Engineering. Vol. 128 (2015).
. Operation and maintenance manual "model 660 series industrial radiography" MAN-006 APRIL 2008.
. Operating and Maintenance Manual " model 880 series industrial radiography " MAN-027-July 2011.
. X-5 Monte Carlo Team" MCNP — A General Monte Carlo
. N-Particle Transport Code, Version 5" April 24, 2003.
. Inspector 1000 " digital hand- held MCA" user's manual
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