Study on the Influence of Stretch-Out Operation on the Deposition of Corrosion Products and Source Term Level in the Primary Circuit of Pressurized Water Reactor

Abstract Corrosion products in the primary circuit of Pressurized Water Reactor (PWR) during operation will cause Chalk Rivers Unidentified Deposit (CRUD), increase level coolant source term and deposition outside core, then affect normal PWR radiation field shutdown overhaul. Stretch-Out (SO) is a flexible mode reactor, which can improve economy reactor. In this paper, theoretical model CRUD analysis for introduced, influence SO on studied. The calculation results show that reduce total amount PWR. However, rises at initial stage operation, be reduced by double discharge pumps running case. reactor gradual increasing trend. research provide basis data reference control