Published 1974 | Version v1
Book Metadata-only

Corrosion of steam generator tubing in operating pressurized water reactors

Creators

  • 1. Atomic Energy Commission, Washington, DC

Description

Corrosion of steam generator tubing has been observed in all but three PWR's that have been in operation for more than one year. The history of this experience with both stainless steel and Inconel-600 tubing is reviewed. Both intergranular stress corrosion cracking and localized, transgranular wastage have been observed with Inconel-600 tubing. The wastage can be attributed to a localized concentration, or ''hideout'' of phosphates in limited flow areas. A model is proposed for this wastage phenomenon which is consistent with operating experience. 33 references

Additional details

Publishing Information

Publisher
Electrochemical Society, Inc.
Imprint Place
Princeton, NJ
Imprint Title
Corrosion problems in energy conversion and generation
Imprint Pagination
p. 322-345.

Conference

Title
Proceedings of the symposium on corrosion problems in energy conversion and generation.
Dates
15 Oct 1974.
Place
New York, New York, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7245002
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
INCONEL 600; PERFORMANCE; PH VALUE; PWR TYPE REACTORS; REACTOR OPERATION; STAINLESS STEELS; STEAM GENERATORS; STRESS CORROSION; TUBES; WATER CHEMISTRY
Descriptors DEC
ALLOYS; BOILERS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; INCONEL ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; OPERATION; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:See CONF-7410138--.