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98169 SCC of Austenitic Stainless Steel, Ni-21Cr-13.5Mo Alloy, and 0.3Mo-O.8Ni-Ti in 350°C Synthetic, NO2-NO3-OH Tank Waste

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Product Number: 51300-98169-SG
ISBN: 98169 1998 CP
Author: Sharad P. Pednekar
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A necessary step in preparation of high-level radioactive tank waste for sate disposal is removal of nonradioactive organic and inorganic components from washed waste. The oxidizing and alkaline nature of most wastes allows the removal of the organic components as water vapor, carbon dioxide, and ammonia gas merely by heating the wastes to no more than 350°C. Type 3 16L stainless steel (UNS S31603) a 21 Cr- 13.5Mo-Ni alloy (UNS N06022), and O.8Ni-0.3Mo-Ti alloy (UNS R53400) were candidate materials for reactors in which the oxidation could be performed. Slow-strain-rate tests were performed on these three materials at a strain rate of... Keywords: Liquid high-level waste, titanium, Ni-Cr-Mo Alloy, SCC, stress corrosion cracking, slow strain rate test, SSRT
A necessary step in preparation of high-level radioactive tank waste for sate disposal is removal of nonradioactive organic and inorganic components from washed waste. The oxidizing and alkaline nature of most wastes allows the removal of the organic components as water vapor, carbon dioxide, and ammonia gas merely by heating the wastes to no more than 350°C. Type 3 16L stainless steel (UNS S31603) a 21 Cr- 13.5Mo-Ni alloy (UNS N06022), and O.8Ni-0.3Mo-Ti alloy (UNS R53400) were candidate materials for reactors in which the oxidation could be performed. Slow-strain-rate tests were performed on these three materials at a strain rate of... Keywords: Liquid high-level waste, titanium, Ni-Cr-Mo Alloy, SCC, stress corrosion cracking, slow strain rate test, SSRT
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