Proceedings of the USNRC/EPRI/ANL Heated Crevice Seminar

Conference · Tue Jun 01 04:00:00 EDT 2004

OSTI ID:835752

An international Heated Crevice Seminar, sponsored by the Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Argonne National Laboratory, and the Electric Power Research Institute, was held at Argonne National Laboratory on October 7-11, 2002. The objective of the seminar was to provide a working forum for the exchange of information by contributing experts on current issues related to corrosion in heated crevices, particularly as it relates to the integrity of pressurized water reactor (PWR) steam generator tubes. Forty-five persons from six countries attended the seminar, including representatives from government agencies, private industry and consultants, government research laboratories, nuclear vendors, and electrical utilities. The seminar opened with keynote talks on secondary-side crevice environments associated with intergranular attack (IGA) and intergranular corrosion cracking (IGSCC) of mill-annealed Alloy 600 steam generator tubes and the submodes of corrosion in heat transfer crevices. This was followed by technical sessions on (1) Corrosion in Crevice Geometries, (2) Experimental Methods, (3) Results from Experimental Studies, and (4) Modeling. The seminar concluded with a panel discussion on the present understanding of corrosive processes in heated crevices and future research needs.

• Research Organization: Electric Power Research Institute, Palo Alto, CA (US)
• Sponsoring Organization: Electric Power Research Institute (EPRI) (US)
• OSTI ID: 835752
• Report Number(s): EPRI--1009355
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
ALLOYS
ANL
CONSULTANTS
CORROSION
CREVICE CORROSION
EPRI
HEAT TRANSFER
INTERGRANULAR CORROSION
INTERGRANULAR STRESS CORROSION CRACKING
MEETINGS
NUCLEAR STEAM GENERATORS
PWR TYPE REACTORS
SIMULATION
STEAM GENERATORS
TUBES