Published 1983 | Version v1
Report Open

Stress-corrosion cracking of Inconel alloy 600 in high-temperature water: an update

Creators

Description

Inconel 600 has been tested in high-temperature aqueous media (without oxygen) in several tests. Data are presented to relate failure times to periods of crack initiation and propagation. Quantitative relationships have been developed from tests in which variations were made in temperature, applied load, strain rate, water chemistry, and the condition of the test alloy

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 - GPO as DE83012218.

Files

14788284.pdf

Files (417.6 kB)

Name Size Download all
md5:c364892359fa3534c96a64ecf9c77bf3
417.6 kB Preview Download

Additional details

Additional titles

Augmented title (English)
PWR

Publishing Information

Imprint Pagination
13 p.
Report number
BNL-NUREG--32912

Conference

Title
Corrosion '83 conference.
Dates
18-22 Apr 1983.
Place
Anaheim, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14788284
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
EXPERIMENTAL DATA; INCONEL 600; INTERGRANULAR CORROSION; PWR TYPE REACTORS; REACTOR MATERIALS; STEAM GENERATORS; STRAINS; STRESS CORROSION; TUBES; WATER CHEMISTRY
Descriptors DEC
ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; DATA; INCONEL ALLOYS; INFORMATION; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; NUMERICAL DATA; REACTORS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT

Optional Information

Secondary number(s)
CONF-830445--3.