Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Electron Accelerator Shielding Design of KIPT Neutron Source Facility

  • Received : 2015.08.06
  • Accepted : 2016.01.06
  • Published : 2016.06.25
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Abstract

The Argonne National Laboratory of the United States and the Kharkov Institute of Physics and Technology of the Ukraine have been collaborating on the design, development and construction of a neutron source facility at Kharkov Institute of Physics and Technology utilizing an electron-accelerator-driven subcritical assembly. The electron beam power is 100 kW using 100-MeV electrons. The facility was designed to perform basic and applied nuclear research, produce medical isotopes, and train nuclear specialists. The biological shield of the accelerator building was designed to reduce the biological dose to less than 5.0e-03 mSv/h during operation. The main source of the biological dose for the accelerator building is the photons and neutrons generated from different interactions of leaked electrons from the electron gun and the accelerator sections with the surrounding components and materials. The Monte Carlo N-particle extended code (MCNPX) was used for the shielding calculations because of its capability to perform electron-, photon-, and neutron-coupled transport simulations. The photon dose was tallied using the MCNPX calculation, starting with the leaked electrons. However, it is difficult to accurately tally the neutron dose directly from the leaked electrons. The neutron yield per electron from the interactions with the surrounding components is very small, ~0.01 neutron for 100-MeV electron and even smaller for lower-energy electrons. This causes difficulties for the Monte Carlo analyses and consumes tremendous computation resources for tallying the neutron dose outside the shield boundary with an acceptable accuracy. To avoid these difficulties, the SOURCE and TALLYX user subroutines of MCNPX were utilized for this study. The generated neutrons were banked, together with all related parameters, for a subsequent MCNPX calculation to obtain the neutron dose. The weight windows variance reduction technique was also utilized for both neutron and photon dose calculations. Two shielding materials, heavy concrete and ordinary concrete, were considered for the shield design. The main goal is to maintain the total dose outside the shield boundary less than 5.0e-03 mSv/h during operation. The shield configuration and parameters of the accelerator building were determined and are presented in this paper.

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References

  1. Y. Gohar, I. Bolshinsky, D. Naberezhnev, Accelerator-driven sub-critical facility: conceptual design development, Nucl. Instr. Meth. Phys. Res. A 562 (2006) 870-874. https://doi.org/10.1016/j.nima.2006.02.158
  2. Denise B. Pelowitz, John S. Hendricks, et al., MCNPX.2.7.B Extension, Los Alamos National Laboratory, 2009. LA-UR-09-04150.
  3. Y.O. Lee, Y.S. Cho, Y.J. Chang, Shielding Aspect of High Current Proton Linear Accelerator (KOMAC), Proceedings of the Korean Nuclear Society Autumn Meeting, Yongpyong (Korea), 2003.
  4. Y.S. Min, C.W. Lee, K.J. Mun, J. Nam, J.Y. Kim, Shielding design for the target room of the Proton Accelerator Research Center, J. Korean Phys. Soc. 56 (2010) 1971. https://doi.org/10.3938/jkps.56.1971
  5. S. Ohnishi, S. Maebara, Y. Sakaki, S. Sato, K. Ochiai, C. Konno, Radiation shielding design for IFMIF/EVEDA accelerator vault, J. Plasma Fusion Res. 9 (2010) 190-192.
  6. M.B. Chadwick, P. Oblozinsky, M. Herman, N.M. Greene, R.D. McKnight, D.L. Smith, P.G. Young, R.E. MacFarlane, G.M. Hale, S.C. Frankle, A.C. Kahler, T. Kawano, R.C. Little, D.G. Madland, P. Moller, R.D. Mosteller, P.R. Page, P. Talou, H. Trellue, M.C. White, W.B. Wilson, R. Arcilla, C.L. Dunford, S.F. Mughabghab, B. Pritychenko, D. Rochman, A.A. Sonzogni, C.R. Lubitz, T.H. Trumbull, J.P. Weinman, D.A. Brown, D.E. Cullen, D.P. Heinrichs, D.P. McNabb, H. Derrien, M.E. Dunn, N.M. Larson, L.C. Leal, A.D. Carlson, R.C. Block, J.B. Briggs, E.T. Cheng, H.C. Huria, M.L. Zerkle, K.S. Kozier, A. Courcelle, V. Pronyaev, S.C. van der Marck, ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology [Internet]. Nucl. Data Sheets 107 (2006) 2932-3061. Available from: http://www.nndc.bnl.gov/endf/b7.0/.
  7. Z. Zhong, Y. Gohar, Shielding design and analysis of KIPT neutron source facility, Prog. Nucl. Energ. 53 (2011) 92. https://doi.org/10.1016/j.pnucene.2010.08.002
  8. Z. Zhong, Y. Gohar, Neutron Source in the MCNPX Shielding Calculation for Electron Driven Facility, Physor 2012, Advances in Reactor Physics, Knoxville (TN), 2012.
  9. Z. Zhong, Y. Gohar, Biological shield design and analysis of KIPT accelerator driven-subcritical facility, Nucl. Technol. 168 (2009) 871. https://doi.org/10.13182/NT168-871
  10. R.G. Williams, C.J. Gesh, R.T. Pagh, Compendium of Material Composition Data for Radiation Transport Modeling, PNNL-15870, Pacific North National Laboratory, 2006.
  11. R.L. Walker, A Summary of Shielding Constant for Concrete, ANL-6443, Argonne National Laboratory, 1961.
  12. C.N. Culbertson, J.S. Hendricks, An Assessment of the MCNP4C Weight Window, LA-13668, Los Alamos National Laboratory, 1999.
  13. International Commission on Radiological Protection, Conversion Coefficients for Use in Radiological Protection Against External Radiation, ICRP Publication 74, Ann. ICRP 26/3-4, 1996.

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