No abstract

Tne Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted for the U.S. Department of Energy (DOE) under the technical direction of the Lawrence Livermore National Laboratory (LLNL). Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980, thus initiating a test with a planned 3-to 5-year fuel storage phase.

Corrosion rates and the mode of corrosion attack form a most important basis for selection of canister materials and design of a nuclear waste package. Type 304L stainless steel was selected as the reference material for canister fabrication because of its generally excellent corrosion resistance in water, steam and air. However, 304L may be susceptible to localized and stress-assisted forms of corrosion under certain conditions. Alternative alloys are also investigated; these alloys were chosen because of their improved resistance to these forms of corrosion. The fabrication and welding processes, as well as the glass pouring operation for defense and commercial high-level wastes, may influence the susceptibility of the canister to localized and stress forms of corrosion.

This is an informal reprt intended primarily for internal or limited external distribution. The opinions and conclusions stated are tliose of the author and may or may not be those of the Laboratory.

Tkis ii i preprint of a paper ialeaara for paUicatiaa n • jwnul ar pnctlawp.! rluates nil be nit before puMicalioa, rbl> ptrpriM a auie available *itb Ik aailmliaeiar, Ihit it mil MM be cited or rrpnaacea' without tat prnaisna of Ike aather.