Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Reactivity feedback effect on loss of flow accident in PWR

  • Foad, Basma (Egypt Nuclear and Radiological Regulatory Authority) ;
  • Abdel-Latif, Salwa H. (Egypt Nuclear and Radiological Regulatory Authority) ;
  • Takeda, Toshikazu (Research Institute of Nuclear Engineering, University of Fukui)
  • Received : 2017.07.18
  • Accepted : 2018.07.19
  • Published : 2018.12.25
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Abstract

In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents. A thermal-hydraulic code coupled with a point reactor kinetic model are used for these calculations; where kinetics parameters have been developed from the neutronic SRAC code to provide inputs to RELAP5-3D code to calculate parameters related to safety and guarantee that they meet the regulatory requirements. In RELAP5-3D the reactivity feedback is computed by both separable and tabular models. The results show the importance of the reactivity feedback on calculating the power which is the key parameter that controls the clad and fuel temperatures to maintain them below their melting point and therefore prevent core melt. In addition, extending modeling capability from separable to tabular model has nonremarkable influence on calculated safety parameters.

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References

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