Measurement of soluble nuclide dissolution rates from spent fuel.

摘要

Gaining a better understanding of the potential release behavior of water-soluble radionuclides is the focus of new laboratory spent fuel dissolution studies being planned in support of the Yucca Mountain Project. Dissolution rates for several soluble nuclides have been measured from spent fuel specimens using static and semi-static methods. Flow-through tests are being developed as a potential supplemental method for determining the matrix component of soluble-nuclide dissolution. Advantages and disadvantages of both semi-static and flow-through methods are discussed. Tests with fuel specimens representing a range of potential fuel states that may occur in the repository, including oxidized fuel, are proposed. Preliminary results from flow-through tests with unirradiated UO(sub 2) suggesting that matrix dissolution rates are very sensitive to water composition are also presented. 7 refs., 6 figs., 2 tabs.