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Calculation of the role of Wigner energy in decontamination of Cs-137 from irradiated Graphite pores ‎

Document Type : Research Article

Authors

1 Nuclear Physics Group, Faculty of Basic Science, Comprehensive University of Imam Hossein, Tehran, Iran

2 Faculty of Nuclear Engineering, University of Shahid Beheshti, Tehran, Iran

3 Chemistry Group, Faculty of Basic Science, Comprehensive University of Imam Hossein, Tehran, Iran

Abstract

During the operation of Graphite -fuel HTGR (High-Temperature Gas-cooled Reactor) nuclear reactors, Graphite  used as a neutron moderator, is irradiated and has a variety of contaminants (such as Cs-137, Co-60, and Sr-90) and due to industrial and environmental considerations, decontamination of irradiated Graphite  is very important. In this study, the decontamination of Cs-137 trapped in Graphite  pores of Graphite -fuel (HTGR) nuclear reactors has been analyzed. The proposed method for decontamination of irradiated Graphite  surfaces is the thermal plasma-sputtering method with noble feed gases, which are used to reduce the risk of radioactive Graphite  waste and in this regard, a mathematical model was developed to describe the process of decontamination of irradiated Graphite, which is prone to release Wigner energy due to defects and torsion caused by radiation. The results show that the decrease in radiation pollution of irradiated Graphite  waste and various parameters of its decontamination process depend on the release of Wigner energy. The results obtained are in good agreement with the other researchers results.

Highlights

  • The decontamination of Cs-137 from irradiated graphite is investigated using the plasma-sputtering method.
  • The results show that the decrease in radiation pollution depends on the release of Wigner energy.
  • This study demonstrates the benefits of using noble gases as a plasma feed gas in the plasma decontamination process.
  • The results can be used to decontamination of various types of irradiated porous materials used in nuclear systems.
  • Researchers of radiation safety, nuclear waste management and nuclear decommissioning will be interested in the results.

Keywords

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Radiation Physics and Engineering
Volume 4, Issue 2
March 2023
Pages 45-51
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History
  • Receive Date: 02 May 2022
  • Revise Date: 02 August 2022
  • Accept Date: 15 August 2022
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