Loss of power accident analysis for the HCCR blanket
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
The blanket system is a crucial element in nuclear fusion power generation, tasked with tritium production and the efficient dissipation of the high thermal flux from the tokamak. Korea is in the process of developing the Helium Cooled Ceramic Reflector (HCCR) blanket, which stands as the forefront design among the nation’s blanket systems. This paper presents accident analysis results of LOOP (Loss Of Offsite Power) accident for the HCCR blanket. Loss of power accident is one of the postulated events in the nuclear fusion system. This event may be caused by common failure of the external electrical grids or electrical faults in the site. The objective of this safety analysis is to assess the impact of the activation of an additional power supply within 90 seconds after an accident on the system temperature, and to evaluate the heat load that can be removed by the stagnated coolant in the CCWS (Component Cooling Water System) connected to the heat exchanger of the blanket system.
Abstract
The blanket system is a crucial element in nuclear fusion power generation, tasked with tritium production and the efficient dissipation of the high thermal flux from the tokamak. Korea is in the process of developing the Helium Cooled Ceramic Reflector (HCCR) blanket, which stands as the forefront design among the nation’s blanket systems. This paper presents accident analysis results of LOOP (Loss Of Offsite Power) accident for the HCCR blanket. Loss of power accident is one of the postulated events in the nuclear fusion system. This event may be caused by common failure of the external electrical grids or electrical faults in the site. The objective of this safety analysis is to assess the impact of the activation of an additional power supply within 90 seconds after an accident on the system temperature, and to evaluate the heat load that can be removed by the stagnated coolant in the CCWS (Component Cooling Water System) connected to the heat exchanger of the blanket system.
참고문헌 (5)
- D. W. Lee, "Current status and R&D plan on ITER TBMs of Korea", J. Kor. Phys. Soc, 49, pp.S340~S344 (2006)
- M. -Y. Ahn, "Current status of accident analysis for Korean HCCR TBS", Fusion Eng. Des, 89, pp.1289~1293 (2014)
- H. G. Jin, "Sensitivity study on in-box LOCA for a Korean HCCR TBM in ITER", Fusion Eng. Des, 89, pp.2024~2027 (2014)
- H. G. Jin, "Scoping study on in-vessel LOCA of a Korean TBS in ITER", IEEE Transaction on plasma science, 42(3), pp.671~674 (2014)
- H. S. Lim, "GAMMA multidimensional multicomponent mixture analysis to predict air ingress phenomena in an HTGR", Nucl. Sci. Eng, 152, pp.87~97 (2006)