SCCIG: a phenomenological model for iodine stress corrosion cracking of Zircaloy. Volume 1. Final report. [PWR; BWR]

Technical Report · Wed Apr 01 00:00:00 EST 1981

DOI:https://doi.org/10.2172/6514101· OSTI ID:6514101

Miller, A. K.; Challenger, K. D.; Tasooji, A.; Ranjan, G. V.; Brooks, G. N.; Eisenberger, M.; Thomas, J. M.

This report presents a new model for iodine stress corrosion cracking (SCC) of Zircaloy, developed as an ingredient of EPRI's SPEAR light-water reactor fuel performance code. The model is based on experimental data generated under related EPRI programs and elsewhere, as well as certain theoretical considerations. It is a unified treatment of SCC crack initiation, crack propagation, and non-SCC fracture, treating such sub-process as intergranular failure, transgranular (cleavage plus fluting) failure, ductile rupture, changes in the local stress and strain distribution due to crack formation and growth, iodine penetration along the SCC crack, and the mutual couplings among these processes.

• Research Organization: Stanford Univ., CA (USA). Dept. of Materials Science and Engineering; Failure Analysis Associates, Palo Alto, CA (USA)
• OSTI ID: 6514101
• Report Number(s): EPRI-NP-1798; TRN: 81-010410
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
REACTOR MATERIALS
PWR TYPE REACTORS
STRESS CORROSION
ZIRCALOY
COMPUTER CALCULATIONS
CRACKS
FUEL CANS
IODINE
MATHEMATICAL MODELS
ALLOYS
CHEMICAL REACTIONS
CORROSION
ELEMENTS
HALOGENS
MATERIALS
NONMETALS
REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360105 - Metals & Alloys- Corrosion & Erosion