Dissolution of Spent Fuel Under the Conditions of Wet Storage and Disposal

by K. S. Chun, Korea Atomic Energy Research Inst, Daejeon, Republic of Korea,
G. I. Park, Korea Atomic Energy Research Inst, Daejeon, Republic of Korea,
H. S. Park, Korea Atomic Energy Research Inst, Daejeon, Republic of Korea,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1991

Abstract: The release of cobalt and cesium from PWR spent fuel rods with three types of artificial defects made on their clads in demineralized water and also the dissolution of uranium from unirradiated CANDU UO2 fuel pellets in several leachants were investigated. The release rate of cesium from the rods might be dependent on the dissolution of UO2 matrix after its initial rapid release, but that of cobalt on the surface dissolution or crud deposited on their clad. And the uranium release in the groundwater and the highly concentrated boric acid solution were quite different from that in demineralized water and the low concentrated boric acid solution, due to the formation of any complex with ions such as CO3-2 and BO3-3 in leachants.

Subject Headings: Fuels | Nuclear power | Uranium | Energy storage | Water resources | Rods | Waste treatment | Acids | Groundwater | North America | Colorado | United States

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