Nuclear Engineering and Technology

  • 제51권5호
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  • Pages.1241-1250
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  • 2019
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Neutronics modeling of bubbles in bubbly flow regime in boiling water reactors

  • Turkmen, Mehmet (Nuclear Engineering Department, Faculty of Engineering, Hacettepe University, Beytepe Campus) ;
  • Tiftikci, Ali (Nuclear Engineering Department, Faculty of Engineering, Sinop University)
  • 투고 : 2018.04.06
  • 심사 : 2019.02.26
  • 발행 : 2019.06.25
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초록

This study mainly focused on the neutronics modeling of bubbles in bubbly flow in boiling water reactors. The bubble, ring and homogenous models were used for radial void fraction distribution. Effect of the bubble and ring models on the infinite multiplication factor and two-group flux distribution was investigated by comparing with the homogenous model. Square pitch unit cell geometry was used in the calculations. In the bubble model, spherical and non-spherical bubbles at random positions, sizes and shapes were produced by Monte Carlo method. The results show that there are significant differences among the proposed models from the viewpoint of physical interaction mechanism. For the fully-developed bubbly flow, $k_{inf}$ is overestimated in the ring model by about $720{\pm}6pcm$ with respect to homogeneous model whereas underestimated in the bubble model by about $-65{\pm}9pcm$ with a standard deviation of 15 pcm. In addition, the ring model shows that the coolant must be separated into regions to properly represent the radial void distribution. Deviations in flux distributions principally occur in certain regions, such as corners. As a result, the bubble model in modeling the void fraction can be used in nuclear engineering calculations.

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참고문헌

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