Advances in materials Research

Techno-Press (테크노프레스)
권호 표지
DOI QR코드

DOI QR Code

Calculation of gamma buildup factors for point sources

  • Received : 2013.11.05
  • Accepted : 2013.02.21
  • Published : 2013.06.25
⟨ Previous Next ⟩

Abstract

Objective of this study is to calculate gamma buildup factors for pointed and isotropic gamma sources in depleted uranium, uranium dioxide, natural uranium, tin, water and concrete using MCNP4C code. The thickness of the media ranges from 0.5 to 10 mean-free-path (mfp) and gamma energy ranges from 0.5 to 10 MeV. Owing to the outstanding accuracy of MCNP in calculation involving gamma interaction, results fairly match those reported previously. The maximum relative error is 2%.

Keywords

References

  1. Bozkurt, A. and Tsoulfanidis, N. (1996) "Exposure buildup factors of UO2 using the Monte Carlo method," Nucl. Sci. Eng., 221, 257-260.
  2. Briesmeister, J.F. (2000), MCNP Monte Carlo N-Particle Transport Code System Los Alamos, National Laboratory.
  3. Jiang, S.H. (1980), "Gamma-ray build up factors for stratified lead and water shields", Nucl. Sci. Eng., 75, 16-29. https://doi.org/10.13182/NSE80-1
  4. Kiyani, A., Rostam, G.Gh., Kiai, S.M.S., Bakhsh, H.J. and Mahdavi, F. (2011), "Measurements of the thermal neutron macroscopic absorption cross section for neutron absorbing layers", J. Fusion Energ., 30, 473-476, DOI 10.1007/s10894-011-9400-9.
  5. Martin, J.E. (2006), Physics for Radiation Protection, 2nd Edition, WILEY-Vch Verlag GmbH & Co. KGaA, Weinheim, 288-289.
  6. Sardari, D., Abbaspour, A., Baradaran, S. and Babapour, F. (2009), "Estimation of gamma- and x-ray photons; buildup factor in soft tissue with Monte Carol method", Appl. Radiat. Isotopes, 67, 1438-1440. https://doi.org/10.1016/j.apradiso.2009.02.033
  7. Shirakawa, Y. (2000), "A build-up treatment for thickness gauging of steel plates based on Gamma-ray transmission", Appl. Radiat. Isotopes, 53, 581-586. https://doi.org/10.1016/S0969-8043(00)00227-X
  8. Shultis, J.K. and Faw, R.E. (2000), Radiation Shielding, American Nuclear Society, p.215.

Cited by

  1. A study of energy absorption and exposure buildup factors in natural uranium vol.4, pp.1, 2015, https://doi.org/10.12989/amr.2015.4.1.23
  2. Comparison of ITO and ZnO ternary glassy composites in terms of radiation shielding properties by Monte Carlo N-particle transport code and BXCOM vol.59, pp.2, 2013, https://doi.org/10.1007/s00411-020-00838-x
  3. Miniaturised Low-Cost Gamma Scanning Platform for Contamination Identification, Localisation and Characterisation: A New Instrument in the Decommissioning Toolkit vol.21, pp.8, 2021, https://doi.org/10.3390/s21082884