Comparative Analysis of Source Term Removal at Cook Nuclear Plant

Source term;source term removal;PWR;Cook Nuclear Plant

Deligiannis, Anastasios ; Miller ; David W.

关键词: Source term;    source term removal;    PWR;    Cook Nuclear Plant;   

Others  :  https://www.ideals.illinois.edu/bitstream/handle/2142/14637/1_Deligiannis_Anastasios.pdf?sequence=3&isAllowed=y

美国|英语

来源: The Illinois Digital Environment for Access to Learning and Scholarship

【 摘 要 】

Research was conducted on the effectiveness of colloid mitigation at the Cook Nuclear Plant located in Bridgman, Michigan.Specialty resin was employed to remove Cobalt-60 CRUD and other contaminates from the primary coolant piping and fuel cladding. Cook is a two unit Ice Condenser Pressurized Water Reactor (Westinghouse). Unit 1 has completed 22 cycles and refueling outages and Unit 2 has completed 18 cycles and refueling outages.Specialty resin was utilitized during the Unit 2 shutdown chemistry protocol to capture and remove Co-60 from the reactor coolant. A CRUD burst was achieved during the first 48 hours of shutdown with the addition of peroxide to achieve significant CRUD removal from the coolant.The study monitored the dose rates on selected in-plant primary loop piping to provide a comprehensive database of the dose rate changes during the shutdown and Crud burst regimes.The database collected represents one of the largest data analysis undertaken for multiple PWR unit outages. Technical comparisons are made of the cycle 16, 17 and 18 telemetry data to demonstrate the improvements in source term removal. Significant source term improvement was observed during the Unit 2, Cycle 18 refueling outage due to successive uses for the specialty resin after full core replacement after 6 cycles, major high source term piping removal in lower containment (RTD bypass line removal) and use of specialty resin on unit startup to remove nickel.Results demonstrate how Cook Unit 2 achieved the lowest record refueling outage dose of 34 person rem for 4 loop, Westinghouse PWR Ice Condenser. The similar PWR outage dose is in the range of 70-90 person rem.The study provides recommendations for future analysis to better understand the radiochemistry phenomena that are working together to achieve this significant reduction in refueling outage doses.