Simulation of long-lived activation products in nuclear reactor biological shield by MCNP and ORIGEN-S

Document Type : Conference Paper

Authors

Department of Physics, Faculty of Sciences, University of Guilan, Rasht, Iran

Abstract

the absorbed dose due to ionizing radiation is a function of three parameters: 1- Time 2- Source 3- Shielding. shielding materials -as any other material- activate when they are exposed to irradiation. The aim of this study is to calculate the attenuation coefficient and investigate shielding properties of different concrete compounds with various aggregates. After that the required time for achieving IAEA anounced clearance levels for these compounds was calculated by ORIGEN-S code.Cs, Co and Eu are important radionucleids in term of determine the required time for achieving clearance levels. 

Keywords


  1. J. S. Walker, T. R. Wellock. A Short History of Nuclear Radiation, 1946-2009. U.S. Nuclear Commission, Washington, 2010.
  2. Biological shield. United States Nuclear Regulatory Commission. http://www.nrc.gov/reading-rm/basic-ref/glossary/biologicalshield.html.Retrieved 13 August 2010.
  3. R. J. Preston. Radiation biology: concepts for radiation protection. Health Phys. 88 (6) (2005) 545-456.
  4. A. B. Chilton, J. K. Shultis, R. E. Few. Principles of Radiation Shielding. Prentice-Hall, Englewood Cliffs, NJ, 1984.
  5. R. S. Keshavamurthy, D. V. Subramanian, R. R. Prasad, A. Haridas, P. Mohanakrishnan, S. C. Chetal. Experimental measurements of neutron attenuation in the advanced shield material ferro - boron in KAMINI reactor. Energy Procedia 7 (2011) 273-278.
  6. D. Sayer, R.Kucer, N. Kucer. Neutron shielding properties of concerts containing boron carbide and Ferro-Boron. World Conf. Tech. Innovation Entrepreneurship 195 (2015) 1752-1756.
  7. L. E. Antonides. Diatomite, U.S.G.S. RetrieVed December 12, 2010.
  8. A. Yadollahi, E. Nazemi, A. Zolfaghari, A. M. Ajorloo. Optimization of thermal neutron shield concrete mixture using artificial neural network. Nucl. Eng. Design 305 (2016) 146-155.
  9. O. Gencel, A. Bozkurt, E. Kam, T. Korkut. Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportions. Ann. Nucl. Energy 38 (12) (2011) 2719–2723.
  10. A. Suzuki,  T. Iida,  J. Moriizumi, Y. Sakuma, J. Takada, K. Yamasaki,  T. Yoshimoto. Trace elements with large activation cross section in concrete materials in Japan, J. Nucl. Sci. Tech. 38 (7) (2001) 542-550.
  11. International Atomic Energy Agency, Application of exemption principles to the Recycle and Reuse of materials from Nuclear Facilities, Safety Series No. 111 P-1.1, IAEA, Vienna, Austria, 1992.