Published 1996 | Version v1
Book Metadata-only

Heated crevice investigation of the effects of feedwater chemistry on crevice chemistry and crevice potential

Creators

  • 1. Rockwell Science Center, Thousand Oaks, CA (United States)
  • 2. Electric Power Research Inst., Palo Alto, CA (United States)

Description

A device has been constructed which mimics the geometry and operating conditions of a tube/tube support plate crevice in a pressurized water reactor (PWR) steam generator. This apparatus is instrumented to measure the tube wall temperature in the crevice, the free span and crevice potentials, and the crevice chemistry. Results have been obtained for 280 C NaOH solutions continuously pumped through the autoclave under several crevice temperature and power levels. Changes in tube wall temperature changes after superheat was applied indicated that various depths in the crevice underwent several thermal-hydraulic transitions before reaching equilibrium conditions. The lower third of the crevice was wetted at equilibrium. Sodium hydroxide concentrated at rates near the theoretical limit until equilibrium was reached at concentration factors in the 104 range

Additional details

Publishing Information

Publisher
NACE International.
Imprint Place
Houston, TX (United States)
Imprint Title
Corrosion/96 conference papers
Imprint Pagination
[6615 p.].
Journal Page Range
p. 9, Paper 111.

Conference

Title
National Association of Corrosion Engineers (NACE) conference.
Acronym
CORROSION '96
Dates
24-29 Mar 1996.
Place
Denver, CO (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27075601
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
CREVICE CORROSION; EXPERIMENTAL DATA; FEEDWATER; MASS TRANSFER; PWR TYPE REACTORS; SODIUM HYDROXIDES; STEAM GENERATORS; TEMPERATURE MEASUREMENT; WATER CHEMISTRY
Descriptors DEC
ALKALI METAL COMPOUNDS; BOILERS; CHEMICAL REACTIONS; CHEMISTRY; CORROSION; DATA; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; HYDROXIDES; INFORMATION; NUMERICAL DATA; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; SODIUM COMPOUNDS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-960389--.