TY - JOUR
T1 - Study of transient events during the full-system chemical decontamination operation of the Kori-1 nuclear power plant
AU - Park, Jea Ho
AU - Cho, Seo Yeon
AU - Kim, Jeong Ju
AU - Kim, Keon Yeop
AU - Bang, Youngsuk
N1 - Publisher Copyright:
© 2022 The Authors
PY - 2022/9/1
Y1 - 2022/9/1
N2 - The Kori-1 nuclear power plant (NPP), a Westinghouse 2-loop pressurized water reactor in Korea, permanently ceased operations on June 18, 2017. Before the main decommissioning activities, full chemical decontamination of primary systems will be performed to secure the safety of workers and minimize the quantity of radioactive waste. In this study, the steady and transient flow characteristics for the chemical decontamination operations were analyzed via a simulation using the Multidimensional Analysis of Reactor Safety, KINS Standard version. Then, based on the accumulated flow mass released from the reactant cooling systems during transient events, the radioactivity levels were estimated using the oxide layer removal ratio obtained from the chemical decontamination experiment. The loss of residual heat removal, steam generator tube rupture (SGTR), power-operated relief valve open (PORV Open), and combination of SGTR and PORV Open simulations were investigated in terms of the transient events. Finally, a strategy for managing transient events during the full-system chemical decontamination operation of the Kori-1 NPP is proposed.
AB - The Kori-1 nuclear power plant (NPP), a Westinghouse 2-loop pressurized water reactor in Korea, permanently ceased operations on June 18, 2017. Before the main decommissioning activities, full chemical decontamination of primary systems will be performed to secure the safety of workers and minimize the quantity of radioactive waste. In this study, the steady and transient flow characteristics for the chemical decontamination operations were analyzed via a simulation using the Multidimensional Analysis of Reactor Safety, KINS Standard version. Then, based on the accumulated flow mass released from the reactant cooling systems during transient events, the radioactivity levels were estimated using the oxide layer removal ratio obtained from the chemical decontamination experiment. The loss of residual heat removal, steam generator tube rupture (SGTR), power-operated relief valve open (PORV Open), and combination of SGTR and PORV Open simulations were investigated in terms of the transient events. Finally, a strategy for managing transient events during the full-system chemical decontamination operation of the Kori-1 NPP is proposed.
KW - Chemical decontamination
KW - Decommissioning
KW - Flow characteristics
KW - Kori-1 nuclear power plant
KW - MARS-KS
KW - Transient analysis
UR - http://www.scopus.com/inward/record.url?scp=85129343664&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2022.109164
DO - 10.1016/j.anucene.2022.109164
M3 - Article
AN - SCOPUS:85129343664
SN - 0306-4549
VL - 174
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 109164
ER -