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Determination of Key Nuclides’ Concentration in Waste Drums of Bushehr Nuclear Power Plant

Dara, Mojtaba | 2014

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 46264 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Samadfam, Mohammad; Otukesh, Mohammad
  7. Abstract:
  8. In this thesis, a computer program is produced to measure the activity of 137Cs and 60Co radionuclides in waste packages generated at Bushehr Nuclear Power Plant (BNPP). In this program, the activity of waste drum was calculated by dividing the waste matrix into very small identical cubic cells, and each cell was considered as a point source (in the center of the cell). The activity was calculated using the theory developed by Krings & Mauerhofer. Detection efficiencies were calculated by the developed program at different conditions of a) different detector distance from drum surface, b) different collimator length, c) different cell size and d) up to 4 segment number. The results were compared with MCNP simulations. In the experimental measurements section, the activities of 137Cs and 60Co radionuclides in an actual waste drum at BNPP were calculated and compared using the results obtained by a gamma scanner system designed and made in this project, BNPP gamma scanner system and Ortec gamma scanner system.
    The experimental results obtained by the manufactured gamma scanner system were in good agreement with those obtained by BNPP gamma scanner system. Differences in the results for 137Cs and 60Co were less than 1% and 14% respectively. The experimental results demonstrate the reliability of the developed program and the gamma scanner system
  9. Keywords:
  10. Nuclear Waste ; Monte Carlo N-Particle (MCNP)Code ; Waste Barrel ; Gamma Scanner ; Segmented Gamma Scanner ; Activity Calculation

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