Evaluation of the susceptibility of ASTM A216 grade WCA mild steel to stress corrosion cracking in simulated salt repository environments

Conference · Mon Sep 01 00:00:00 EDT 1986

OSTI ID:7225395

Pitman, S G

In current conceptual designs, a mild steel (ASTM A216 Grade WCA) is the reference container material for use in high level nuclear waste packages intended for emplacement in a salt repository. The resistance of the steel to stress corrosion cracking (SCC) is being investigated as part of the effort underway to verify the suitability of the material for waste package applications. Static tests (U-bend and bolt-loaded fracture toughness specimens) and dynamic tests (slow strain rate and corrosion fatigue) were conducted on both as-cast and weldment specimens of the material, in both low-Mg and high-Mg halite-saturated brines, in the temperature range of 90 to 200/sup 0/C. The investigations indicate that the steel is not susceptible to SCC under the test conditions employed.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 7225395
• Report Number(s): PNL-SA-14218; CONF-861207-18; ON: DE87002871
• Resource Relation: Conference: Materials Research Society fall meeting, Boston, MA, USA, 1 Dec 1986; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE STORAGE
CONTAINERS
STEELS
CORROSION RESISTANCE
BRINES
HIGH TEMPERATURE
HIGH-LEVEL RADIOACTIVE WASTES
MATERIALS TESTING
MEDIUM TEMPERATURE
STRAIN RATE
STRESS CORROSION
ALLOYS
CHEMICAL REACTIONS
CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MANAGEMENT
MATERIALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
STORAGE
TESTING
WASTE MANAGEMENT
WASTE STORAGE
WASTES
360105* - Metals & Alloys- Corrosion & Erosion
052002 - Nuclear Fuels- Waste Disposal & Storage