SCC of austenitic stainless steel, Ni-21Cr-13.5Mo alloy, and 0.3Mo-0.8Ni-Ti in 350 C synthetic, NO{sub 2}2-NO{sub 3}-OH tank waste

Conference · Thu Dec 31 00:00:00 EST 1998

OSTI ID:352574

Pednekar, S P ^[1]

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1. Army Research Lab., Aberdeen Proving Ground, MD (United States)

A necessary step in preparation of high-level radioactive tank waste for sate disposal is removal of non radioactive 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 S3 1603) a 21Cr-13.5Mo-Ni alloy (UNS N06022), and 0.8Ni-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 10{sup {minus}6}sec{sup {minus}1} in a diluted waste type solution containing 4.1% NO{sub 2}, 3.7% NO{sub 3}, 1% OH, and 0.22% TIC. All three materials showed intergranular stress corrosion cracking with substantial losses in ductility and strength.

• OSTI ID: 352574
• Report Number(s): CONF-980316-; TRN: IM9928%%168
• Resource Relation: Conference: Corrosion `98, San Diego, CA (United States), 22-27 Mar 1998; Other Information: PBD: 1998; Related Information: Is Part Of Corrosion `98: 53. annual conference and exposition, proceedings; PB: [6600] p.
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
05 NUCLEAR FUELS
RADIOACTIVE WASTE PROCESSING
HIGH-LEVEL RADIOACTIVE WASTES
REMOVAL
ORGANIC COMPOUNDS
TITANIUM BASE ALLOYS
NICKEL BASE ALLOYS
CHROMIUM ALLOYS
MOLYBDENUM ALLOYS
STAINLESS STEEL-316L
OXIDATION
CHEMICAL REACTORS
STRESS CORROSION
CRACK PROPAGATION
HANFORD RESERVATION