Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Monte Carlo simulation of the possibility of cobalt-60 production in Tehran research reactor

Document Type : Research Paper

Authors

Z. Gholamzadeh
B. Rok Rok

Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.BOX: 14395-836, Tehran – Iran

https://doi.org/10.24200/nst.2024.1568
Abstract
60Co is used as a major industrial radioactive source in food and medical equipment sterilization. KCi sources can be used for laboratory research, however, few industrial centers utilize these sources for irradiating agricultural products. Hence, in this study, the potential of producing tens of kCi from 60Co sources in the Tehran research reactor has been investigated through the MCNPX code. Different assemblies including 59Co rods were modeled by a computational code. In addition, the loading of the 59Co rod assembly in different arrangements of the Tehran research reactor core was investigated. The 59Co production yield was calculated in each case. The results of this study show that by optimizing the 59Co rod assembly in a 27-fuel 1401-year core arrangement of the Tehran Research Reactor, it is possible to achieve about 40 kCi of 60Co product after 3 years of irradiation. The use of a beryllium reflector with optimized geometry can reduce the negative reactivity caused by the 59Co assembly loading. Also, loading the cobalt-59 assembly at the periphery of the equilibrium core of the Tehran research reactor can lead to the production of about 23 kCi of cobalt-60.

Highlights

  1. https://nucleus.iaea.org/sites/diif/Pages/GammaRT.aspx.

 

  1. Bagheri R, Ranjbar H. Nuclear Designing of a Blood Irradiator Facility for Research and Medical Applications Using Cobalt-60 Line Sources. Scientific Quarterly of Applied Physics of Iran, School of Physics, Al-Zahra University. (12th year, consecutive 13, winter 1401).

 

  1. Fernandes Â, Antonio A.L, Oliveira B, Martins A. Effects of gamma rays on sugars composition of wild mushrooms from the Northeast of Portugal. International Conference of Agricultural Engineering. (Valencia, 2012).

 

  1. Baccaro S, Cemmi A, Sarcina I.Di, Ferrara G. Gamma Irradiation CALLIOPE Facility at ENEA Casaccia Research Centre. 2019.

 

  1. Khalafi H, Gharib M. Optimization of 60Co production using neutron flux trap in the Tehran research reactor. Annal. of Nucl. Energ. 2005;32:331.

 

  1. Judaibi A, Soliman A.Y. Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code. Kerntechnik. 2022;87(2):230.

 

  1. Manual for reactor produced radioisotopes. (IAEA-TECDOC-1340. 2003).

 

  1. Zhijian C, Yunjiang S, Chunchua Z, Maoling Li. Recent status on cobalt-60 gamma ray radiation sources production and its application in China. Redint. Phys. Chem. 1993;42(1-3):469.

 

  1. George J.R, Kushwah R, Sastry K.V.S. Teletherapy sources with imported and indigenous 60Co activity. Journal of Med. Phys. 2009;34(3):180.

 

  1. https://parsisotope-industrial.com/product/60-Cobalt.

 

  1. Pelowitz D.B. Users′ manual versión of MCNPX2.6.0. (LANL, LA-CP-07-1473. 2008).

 

  1. Shultis J.K, Faw R.E. An MCNP primer Dept. of Mechanical and Nuclear Engineering. (Kansas State University. Copyright. 2004-2010).

 

  1. Briesmeister J.F. MCNP- A General Monte Carlo N-Particle Transport code Version4C. (Los Alamos National Laboratory Report, USA, LA-13709-M 2000).

 

  1. Gallmeier F.X, Ferguson P.D, Lu W, Iverson E.B, Muhrer G, Holloway S.T, Kelsey Ch, Pitcher E, Wohlmuther M, Micklich B. The CINDER’90 transmutation code package for use in accelerator applications in combination with MCNPX. (19th Meeting on Collaboration of Advanced Neutron Sources. 2010).

 

  1. Fensin M.L. Development of the MCNPX depletion capability: A Monte Carlo linked depletion method that automates the coupling between MCNPX and CINDER90 for high fidelity burnup calculations. (University of Florida. 2008).

 

  1. Gholazadeh Z, Khoshahval F, Mozafari M.A, Joze-Vaziri A. Computational investigation of Tehran research reactor graphite reflector replacement with Be, BeO or D2O and its impacts on thermal neutron flux enhancement. International Journal of Nuclear Energy Science and Technology. 2019;13(4):350.

 

  1. Introduction and general description of research reactor. (TRR- SA- RPT- 052).

Keywords

Feasibility study
60Co
kCi source
MCNPX
  1. https://nucleus.iaea.org/sites/diif/Pages/GammaRT.aspx.

 

  1. Bagheri R, Ranjbar H. Nuclear Designing of a Blood Irradiator Facility for Research and Medical Applications Using Cobalt-60 Line Sources. Scientific Quarterly of Applied Physics of Iran, School of Physics, Al-Zahra University. (12th year, consecutive 13, winter 1401).

 

  1. Fernandes Â, Antonio A.L, Oliveira B, Martins A. Effects of gamma rays on sugars composition of wild mushrooms from the Northeast of Portugal. International Conference of Agricultural Engineering. (Valencia, 2012).

 

  1. Baccaro S, Cemmi A, Sarcina I.Di, Ferrara G. Gamma Irradiation CALLIOPE Facility at ENEA Casaccia Research Centre. 2019.

 

  1. Khalafi H, Gharib M. Optimization of 60Co production using neutron flux trap in the Tehran research reactor. Annal. of Nucl. Energ. 2005;32:331.

 

  1. Judaibi A, Soliman A.Y. Simulation of cobalt-60 production in research reactors using OpenMC Monte Carlo code. Kerntechnik. 2022;87(2):230.

 

  1. Manual for reactor produced radioisotopes. (IAEA-TECDOC-1340. 2003).

 

  1. Zhijian C, Yunjiang S, Chunchua Z, Maoling Li. Recent status on cobalt-60 gamma ray radiation sources production and its application in China. Redint. Phys. Chem. 1993;42(1-3):469.

 

  1. George J.R, Kushwah R, Sastry K.V.S. Teletherapy sources with imported and indigenous 60Co activity. Journal of Med. Phys. 2009;34(3):180.

 

  1. https://parsisotope-industrial.com/product/60-Cobalt.

 

  1. Pelowitz D.B. Users′ manual versión of MCNPX2.6.0. (LANL, LA-CP-07-1473. 2008).

 

  1. Shultis J.K, Faw R.E. An MCNP primer Dept. of Mechanical and Nuclear Engineering. (Kansas State University. Copyright. 2004-2010).

 

  1. Briesmeister J.F. MCNP- A General Monte Carlo N-Particle Transport code Version4C. (Los Alamos National Laboratory Report, USA, LA-13709-M 2000).

 

  1. Gallmeier F.X, Ferguson P.D, Lu W, Iverson E.B, Muhrer G, Holloway S.T, Kelsey Ch, Pitcher E, Wohlmuther M, Micklich B. The CINDER’90 transmutation code package for use in accelerator applications in combination with MCNPX. (19th Meeting on Collaboration of Advanced Neutron Sources. 2010).

 

  1. Fensin M.L. Development of the MCNPX depletion capability: A Monte Carlo linked depletion method that automates the coupling between MCNPX and CINDER90 for high fidelity burnup calculations. (University of Florida. 2008).

 

  1. Gholazadeh Z, Khoshahval F, Mozafari M.A, Joze-Vaziri A. Computational investigation of Tehran research reactor graphite reflector replacement with Be, BeO or D2O and its impacts on thermal neutron flux enhancement. International Journal of Nuclear Energy Science and Technology. 2019;13(4):350.

 

  1. Introduction and general description of research reactor. (TRR- SA- RPT- 052).

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