Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Determination of plutonium and uranium content and burnup using six group delayed neutrons

  • Akyurek, T. (Department of Physics, Faculty of Art and Science, Marmara University) ;
  • Usman, S. (Department of Mining and Nuclear Engineering, Missouri University of Science & Technology)
  • Received : 2018.08.13
  • Accepted : 2019.01.08
  • Published : 2019.05.25
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Abstract

In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium free fuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. $^{239}Pu$ conversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively.

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References

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