Assessment of Release Rates for Radionuclides in Activated Concrete.

Sullivan, T. M.

Brookhaven National Laboratory

关键词: Radionuclide Migration;    Waste Forms;    Concretes;    12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities;    Radioisotopes;   

DOI  :  10.2172/15006619
RP-ID  :  BNL--71537-2003
RP-ID  :  AC02-98CH10886
RP-ID  :  15006619

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Maine Yankee (MY) nuclear power plant is undergoing the process of decontamination and decommissioning (D&D). Part of the process requires analyses that demonstrate that any radioactivity that remains after D&D will not cause exposure to radioactive contaminants to exceed acceptable limits. This requires knowledge of the distribution of radionuclides in the remaining material and their potential release mechanisms from the material to the contacting groundwater. In this study the concern involves radionuclide contamination in activated concrete in the ICI Sump below the containment building. Figures 1-3 are schematic representations of the ICI Sump. Figure 2 and 3 contain the relevant dimensions needed for the analysis. The key features of Figures 2 and 3 are the 3/8-inch carbon steel liner that isolates the activated concrete from the pit and the concrete wall, which is between 7 feet and 7 feet 2 inches thick. During operations, a small neutron flux from the reactor activated the carbon steel liner and the concrete outside the liner. Current MY plans call for filling the ICI sump with compacted sand.