Speaker
Mu-Young Ahn
(National Fusion Research Institute)
Description
Korean Helium Cooled Ceramic Reflector (HCCR) Test Blanket System (TBS) will be operated at elevated temperature with high pressure helium coolant during normal operation in ITER. One of the main ancillary systems of HCCR-TBS is Helium Cooling System (HCS) which play an important role to extract heat from HCCR Test Blanket Module (TBM) by the helium coolant to keep the operational temperature and the extracted heat is finally transferred to ITER CCWS-1 (Component Cooling Water System) by a Printed Circuit Heat Exchanger (PCHE) in the HCS. In such circumstances if Loss Of Coolant Accident (LOCA) occurs in the PCHE, the high pressure helium coolant in the primary side goes into low pressure water in the secondary side thus pressurizing CCWS-1. In addition, since the helium coolant contains tritium due to permeation from the TBM, tritium migrates into CCWS-1, a non-nuclear system. In this paper, accident analysis for LOCA in the heat exchanger is presented. For the analysis, GAMMA-FR code which has been developed for fusion applications was used. Main components in the HCS and CCWS-1 were modelled as volume and junctions. The accident analysis was performed for the reference case with ten channels rupture and sensitivity study was also performed by changing the crack size. The results show that pressure and tritium requirement of CCWS-1 can be met in spite of LOCA in the heat exchanger of the HCCR-TBS HCS.
Co-authors
Dong Won Lee
(Korea Atomic Energy Research Institute, Daejeon, South Korea)
Hyung Gon Jin
(Korea Atomic Energy Research Institute, Daejeon, South Korea)
Mu-Young Ahn
(National Fusion Research Institute, Daejeon, South Korea)
Seungyon Cho
(National Fusion Research Institute, Daejeon, South Korea)
Yi-Hyun Park
(National Fusion Research Institute, Daejeon, South Korea)
Youngmin Lee
(National Fusion Research Institute, Daejeon, South Korea)
