Prevention of wear problems in PWR steam generators - an annotated bibliography. Final report

Technical Report · Fri Oct 01 04:00:00 EDT 1982

OSTI ID:6758343

Conn, A F

Specific wear mechanisms which may be among the initiating causes for loss of tube integrity in the steam generators of pressurized water reactors (PWR) are reviewed. These mechanisms are: solid particle impact erosion, liquid droplet impact erosion, cavitation erosion, fretting, erosion-corrosion, and other electro-chemical phenomena. The reviews, in the form of annotated bibliographies, focus on studies which involved either materials and/or geometries and operating conditions relevant to PWR steam generators. The objective of this study was to provide a state-of-the-art documentation of the literature on wear mechanisms - thus enabling either a researcher, vendor, or utility to more readily locate further information about his specific concerns.

• Research Organization: Hydronautics, Inc., Laurel, MD (USA)
• OSTI ID: 6758343
• Report Number(s): EPRI-NP-2711; ON: DE83900530
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BIBLIOGRAPHIES
BOILERS
DOCUMENT TYPES
EROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
PERFORMANCE
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEAM GENERATORS
STEELS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR