Nuclear Engineering and Technology

  • 제51권5호
  • /
  • Pages.1272-1278
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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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An approach to the coupled dynamics of small lead cooled fast reactors

  • Zarei, M. (Engineering Department, Shahid Beheshti University)
  • 투고 : 2018.07.20
  • 심사 : 2019.03.20
  • 발행 : 2019.06.25
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초록

A lumped kinetic modeling platform is developed to investigate the coupled nuclear/thermo-fluid features of the closed natural circulation loop in a low power lead cooled fast reactor. This coolant material serves a reliable choice with noticeable thermo-physical safety characteristics in terms of natural convection. Boussienesq approximation is resorted to appropriately reduce the governing partial differential equations (PDEs) for the fluid flow into a set of ordinary differential equations (ODEs). As a main contributing step, the coolant circulation speed is accordingly correlated to the loop operational power and temperature levels. Further temporal analysis and control synthesis activities may thus be carried out within a more consistent state space framework. Nyquist stability criterion is thereafter employed to carry out a sensitivity analysis for the system stability at various power and heat sink temperature levels and results confirm a widely stable natural circulation loop.

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참고문헌

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피인용 문헌

  1. On Singular Perturbation of Neutron Point Kinetics in the Dynamic Model of a PWR Nuclear Power Plant vol.2, pp.2, 2019, https://doi.org/10.3390/sci2020030
  2. On Singular Perturbation of Neutron Point Kinetics in the Dynamic Model of a PWR Nuclear Power Plant vol.2, pp.2, 2020, https://doi.org/10.3390/sci2020036