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Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator

  • Abdelhameed, Ahmed Amin E. (Department of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technolog) ;
  • Chaudri, Khurrum Saleem (Department of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technolog) ;
  • Kim, Yonghee (Department of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technolog)
  • Received : 2020.02.06
  • Accepted : 2020.05.11
  • Published : 2020.12.25

Abstract

Helical-coil steam generator (HCSG) technology is a major design candidate for small modular reactors due to its compactness and capability to produce superheated steam with high generation efficiency. In this paper, we investigate the feasibility of the passively autonomous power maneuvering by coupling the 3-D transient multi-physics of a soluble-boron-free (SBF) core with a time-dependent HCSG model. The predictor corrector quasi-static method was used to reduce the cost of the transient 3-D neutronic solution. In the numerical system simulations, the feedwater flow rate to the secondary of the HCSGs is adjusted to extract the demanded power from the primary loop. This varies the coolant temperature at the inlet of the SBF core, which governs the passively autonomous power maneuvering due to the strongly negative coolant reactivity feedback. Here, we simulate a 100-50-100 load-follow operation with a 5%/minute power ramping speed to investigate the feasibility of the passively autonomous load-follow in a 450 MWth SBF PWR. In addition, the passively autonomous frequency control operation is investigated. The various system models are coupled, and they are solved by an in-house Fortran-95 code. The results of this work demonstrate constant steam temperature in the secondary side and limited variation of the primary coolant temperature. Meanwhile, the variations of the core axial shape index and the core power peaking are sufficiently small.

Keywords

Acknowledgement

The National Research Foundation of Korea (NRF) Grant funded by the Korean Government (MSIP) (NRF-2016R1A5A1013919) supported this work.

References

  1. A. Lokhov, Technical and Economic Aspects of Load Following with Nuclear Power Plants, NEA, OECD, Paris, France, 2011.
  2. A.A.E. Abdelhameed, J. Lee, Y. Kim, Physics conditions of passive autonomous frequency control operation in conventional large-size PWRs, Prog. Nucl. Energy 118 (2020) 103072.
  3. Y.-H. Kim, et al., Load follow performance of KNGR using an extended mode-K control logic, in: Proceedings of the Korean Nuclear Society Conference, Korean Nuclear Society, 1999.
  4. S.-Y. Oh, et al., Mode Kda core control logic for enhanced load-follow operations of a pressurized water reactor, Nucl. Technol. 134 (2) (2001) 196-207.
  5. A.A.E. Abdelhameed, et al., Feasibility of passive autonomous frequency control operation in a Soluble-Boron-Free small PWR, Ann. Nucl. Energy 116 (2018) 319-333.
  6. X.H. Nguyen, C. Kim, Y. Kim, An advanced core design for a soluble-boron-free small modular reactor ATOM with centrally-shielded burnable absorber, Nuclear Engineering and Technology 51 (2) (2019) 369-376.
  7. A.A.E. Abdelhameed, Y. Kim, Three-dimensional simulation of passive frequency regulations in the soluble-boron-free SMR ATOM, Nuclear Engineering and Design, 2020, p. 110505.
  8. J. Leppanen, Serpent-a Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code, vol. 4, VTT Technical Research Centre of Finland, 2013.
  9. B. Christensen, Three-dimensional static and dynamic reactor calculations by the nodal expansion method, Risoe National Lab, 1985.
  10. S. Dulla, E.H. Mund, P. Ravetto, The quasi-static method revisited, Prog. Nucl. Energy 50 (8) (2008) 908-920.
  11. Y. Jo, B. Cho, N.Z. Cho, Nuclear reactor transient analysis by continuous-energy Monte Carlo calculation based on predictor-corrector quasi-static method, Nucl. Sci. Eng. 183 (2) (2016) 229-246.
  12. K.S. Chaudri, J. Kim, Y. Kim, Development and validation of a fast sub-channel code for LWR multi-physics analyses, Nuclear Engineering and Technology, 2019.
  13. E. Brega, E. Salina, COBRA-EN, Thermal-Hydraulic Transient Analysis of Reactor Cores, 2001.

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