Laboratory evaluation of low cobalt wear materials for nuclear applications
- 1. Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab.
Description
The wear and corrosion of high cobalt wear resistant alloys, commonly used in nuclear power plant components, represents a significant source of cobalt contamination to the primary coolant system. Replacement of these materials with cobalt free alloys will result in a significant reduction in post-shutdown radiation fields and associated occupational radiation exposures. Several materials screening programs have been performed world-wide and have resulted in the selection of a variety of cobalt-free alloys, particularly for valve applications. The NOREM series of alloys, developed on an Electric Power Research Institute (EPRI) sponsored program, along with other candidates alloys, were tested in gate valves in an EPRI sponsored program run by the Atomic Energy of Canada Limited. A screening program run in the UK resulted in the selection of Delcrome 910 for valve applications. A similar alloy, Everit 50 was selected for use in the German PWR program. The program reported here evaluated the wear behavior of some of the same alloys. Corrosion tests were also performed with special attention being given to simulated off-normal chemistries such as storage and wet-lay up, decontamination and air-accident conditions. (authors). 5 figs., 3 tabs., 4 refs
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors. Volume 1
- Imprint Pagination
- 404 p.
- Journal Page Range
- p. 99-106.
Conference
- Title
- International Symposium on the Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors.
- Dates
- 12-16 Sep 1994.
- Place
- Fontevraud (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 26071675
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLMONOY; CORROSION RESISTANCE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SLIDING FRICTION; STEEL-CR25; STELLITE 6; TESTING; WEAR RESISTANCE
- Descriptors DEC
- ALLOY-CO60CR30W4; ALLOYS; BORON ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; COBALT ALLOYS; COBALT BASE ALLOYS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FERRITIC STEELS; FRICTION; HAYNES ALLOYS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SILICON ALLOYS; STAINLESS STEELS; STEELS; STELLITE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUNGSTEN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS