Boundary condition coupling methods and its application to BOP-integrated transient simulation of SMART
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
The load-following operation of small modular reactors (SMRs) requires accurate prediction of transient behaviors that can occur in the balance of plants (BOP) and the nuclear steam supply system (NSSS). However, 1-D thermal-hydraulics analysis codes developed for safety and performance analysis have conventionally excluded the BOP from the simulation by assuming ideal boundary conditions for the main steam and feed water (MS/FW) systems, i.e., an open loop. In this study, we introduced a lumped model of BOP fluid system and coupled it with NSSS without any ideal boundary conditions, i.e., in a closed loop. Various methods for coupling boundary conditions at MS/FW were tested to validate their combination in terms of minimizing numerical instability, which mainly arises from the coupled boundaries. The method exhibiting the best performance was selected and applied to a transient simulation of an integrated NSSS and BOP system of a SMART. For a transient event with core power change of 100e20-100%, the simulation exhibited numerical stability throughout the system without any significant perturbation of thermal-hydraulic parameters. Thus, the introduced boundary-condition coupling method and BOP fluid system model can expectedly be employed for the transient simulation and performance analysis of SMRs requiring daily load-following operations
Abstract
The load-following operation of small modular reactors (SMRs) requires accurate prediction of transient behaviors that can occur in the balance of plants (BOP) and the nuclear steam supply system (NSSS). However, 1-D thermal-hydraulics analysis codes developed for safety and performance analysis have conventionally excluded the BOP from the simulation by assuming ideal boundary conditions for the main steam and feed water (MS/FW) systems, i.e., an open loop. In this study, we introduced a lumped model of BOP fluid system and coupled it with NSSS without any ideal boundary conditions, i.e., in a closed loop. Various methods for coupling boundary conditions at MS/FW were tested to validate their combination in terms of minimizing numerical instability, which mainly arises from the coupled boundaries. The method exhibiting the best performance was selected and applied to a transient simulation of an integrated NSSS and BOP system of a SMART. For a transient event with core power change of 100e20-100%, the simulation exhibited numerical stability throughout the system without any significant perturbation of thermal-hydraulic parameters. Thus, the introduced boundary-condition coupling method and BOP fluid system model can expectedly be employed for the transient simulation and performance analysis of SMRs requiring daily load-following operations
참고문헌 (15)
- G. Locatelli, "Load following with small modular reactors(SMR) : a real options analysis", Energy, 80, pp.41~54 (2015)
- B. Poudel, "A dynamic model of small modular reactors based nuclear plant for power system studies", IEEE Trans. Eng. Conv, 35, pp.997~ (2020)
- J. H. Chun, "Assessment and SMART application of system analysis code", TASS, 2013, pp.254, 291~299
- H. -K. Kim, "Thermal-hydraulic analysis for SMART steam generator tube rupture using TASS", SMR-S code, 2013, pp.55, 331~340
- Y. -J. Chung, "Validation with the MARS and TASS", SMR codes based on experimental results of a pressurizer safety valve line break at the SMART-ITL facility, 2020, pp.141, 107344~
- 배황, "Experimental investigation and validation of TASS", SMR-S code for single-phase and two-phase natural circulation tests with SMART-ITL facility, 2022, pp.54(2), 554~564[DOI]
- K. D. Kim, "A web-based nuclear simulator using RELAP5 and Lab-VIEW", Nucl. Eng. Des, 237, pp.1185~1194 (2007)
- C. -Y. Yang, "Development and application of a dual RELAP5-3D-based engineering simulator for ABWR", Nucl. Eng. Des, 239, pp.1847~1856 (2009)
- R. Schmidt, "An approach for coupled-code multiphysics core simulations from a common input", Ann. Nucl. Energy, 84, pp.140~152 (2015)
- K. Zhang, "The multiscale thermal-hydraulic simulation for nuclear reactors : a classification of the coupling approaches and a review of the coupled codes", Energy Res, 44, pp.3295~3315 (2020)
- R. K. Salko, "Optimization and parallelization of the thermal-hydraulic subchannel code CTF for high-fidelity multi-physics applications", Ann. Nucl. Energy, 84, pp.122~130 (2015)
- Y. J. Chung, "Development and assessment of system analysis code, TASS", SMR for integral reactor, SMART, 2012, pp.244, 52~60
- J. Liu, "A new measurement model for main steam flow of power plants", Proc. Environ. Sci, 11, pp.18~24 (2011)
- E.W. Lemmon, "NIST Standard Reference Database 23: Reference Fluid Thermodynamic and Transport Properties-REFPROP, Version 8.0" (2007), National Institute of Standards and Technology
- SMART Standard Safety Analysis Report, "KEPCO", SSAR, ~ (2010)
