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

Dose Rate Calculation of Radiation Emitted from 30B Cylinder Containing Natural UF6

Document Type : Research Paper

Authors

M Vafabakhsh
A Rahimi
A.H Taherizadeh Saghand
H Havasi
Abstract
Dose rate is one of the most important factors that should be considered in handling, stacking and transportation of nuclear materials for the occupational radiation protection and for the people who are exposing to. Uranium hexafluoride is one of the radioactive compounds of uranium which is used in the enrichment industry. UF6 is kept and transferred in special carbon steel containers. In this study, the absorbed dose of radiations emitted from 30B cylinder containing fully-aged natural UF6 is simulated by MCNP4C code and results are compared with the actual data. The absorbed dose rate depends on some factors such as cylinder contents, storage time before and after discharge, radiation energy, geometry, the enrichment percent, etc. The satisfactory consistency between the calculations and measurements confirms that the simulation model can contribute to the dose mapping data around the UF6 cylinder and can be used for determination of the allowable exposure time and to control absorbed dose rate. This study is performed experimentally at the KALA ELECTRIC Company.

Highlights

  1. J.G. LEWI, “Dose rates produced from gamma ray sources,” Industrial and Engineering Chemistry, V. 49 (1957).

     

  2. Jack, C. Bailey, “Health physics considerations in UF6 handling,” CONF-9110117 (1991).

     

  3. P.J. Friend, “Radiation dose rates from UF6 cylinders,” CONF-9110117 (1991).

     

  4. Judith F. Briesmeister, Editor, MCNP–A General Monte Carlo N–Particle Transport Code Version 4C, April 10 (2000).

     

  5. P.H.G.M. Hendriks, M. Maučec1, R.J. de Meijer, “MCNP modeling of scintillation-detector γ-ray spectra from natural radionuclides,” Applied Radiation and Isotopes, 57, 449–457 (2002).

     

     

     

     

     

     

  6. C. Oliveira, J. Salgado, A. Ferro de Carvalho, “Dose rate determinations in the Portuguese Gamma Irradiation Facility, Monte Carlo Simulations and Measurements,” Radiation Physics and Chemistry 58, 279-285 (2000).

     

  7. DOE-Std-1136-2004, “Guide of good practices for occupotional Radiological protection in uranium pocilities,” December (2004).

     

  8. Cember Herman, “Introduction to Health Physics,” McGraw-Hill (1996).

     

  9. Kenneth S. Krane, “Introductory Nuclear Physics,” John Wiley & Sons (1988).

     

  10. M. Ghiasi Nezhad, M. Katoozi, “General courses on radiation protection,” Dorbid (2003).

     

Keywords

MCNP
Dose Rate
Radioactivity
Uranium Hexafluoride
UF6 Cylinder

  1. J.G. LEWI, “Dose rates produced from gamma ray sources,” Industrial and Engineering Chemistry, V. 49 (1957).

     

  2. Jack, C. Bailey, “Health physics considerations in UF6 handling,” CONF-9110117 (1991).

     

  3. P.J. Friend, “Radiation dose rates from UF6 cylinders,” CONF-9110117 (1991).

     

  4. Judith F. Briesmeister, Editor, MCNP–A General Monte Carlo N–Particle Transport Code Version 4C, April 10 (2000).

     

  5. P.H.G.M. Hendriks, M. Maučec1, R.J. de Meijer, “MCNP modeling of scintillation-detector γ-ray spectra from natural radionuclides,” Applied Radiation and Isotopes, 57, 449–457 (2002).

     

     

     

     

     

     

  6. C. Oliveira, J. Salgado, A. Ferro de Carvalho, “Dose rate determinations in the Portuguese Gamma Irradiation Facility, Monte Carlo Simulations and Measurements,” Radiation Physics and Chemistry 58, 279-285 (2000).

     

  7. DOE-Std-1136-2004, “Guide of good practices for occupotional Radiological protection in uranium pocilities,” December (2004).

     

  8. Cember Herman, “Introduction to Health Physics,” McGraw-Hill (1996).

     

  9. Kenneth S. Krane, “Introductory Nuclear Physics,” John Wiley & Sons (1988).

     

  10. M. Ghiasi Nezhad, M. Katoozi, “General courses on radiation protection,” Dorbid (2003).

     

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