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Laboratory Simulation of Crud Deposition on Zr-alloy Fuel Cladding in Simulated Pressurized Water Reactor Primary Coolant |
LIAO Jiapeng( ), MAO Yulong, JIN Desheng, LI Jinggang |
China Nuclear Power Technology Research Institute, Shenzhen 518000, China |
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Abstract For pressurized water reactor (PWR) nuclear power plant, crud on fuel cladding is derived from primary corrosion products, which deposit on the surface of fuel assembly. Crud deposition is affected by the coupling effects between the primary coolant environment and the thermal-hydraulic condition. The crud on cladding surface can affect the operation safety and economic benefits of the reactor. In this paper, the main factors affecting the crud deposition behavior on the surface of fuel cladding were described. The crud deposition process on the domestic Zr-alloy cladding was assessed via a home-made experimental set. As a result, the porous and chimney-like crud was successfully reproduced, while which composed mainly of NiFe2O4, Fe2O3 and NiO, besides the precipitation of LiBO2 was detected. The experiment results indicated that the crud deposition on PWR fuel cladding could be reliably reproduced through laboratory simulation.
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Received: 18 January 2022
32134.14.1005.4537.2022.022
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Fund: China Postdoctoral Science Foundation(2021M703023) |
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