Published October 1988 | Version v1
Report Open

Initial assessment of the processes and significance of thermal aging in cast stainless steels

Creators

Description

Charpy-impact and J-R curve data for thermally aged cast stainless steel are presented. The effects of material variables on the embrittlement of cast materials are evaluated. The chemical composition and ferrite morphology have a strong effect on the kinetics and extent of embrittlement. The procedure and correlations for predicting the impact strength and fracture toughness of cast component during reactor service are described. 19 refs., 17 figs., 4 tabs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 - OSTI; 1 as DE89003633.

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Additional details

Publishing Information

Imprint Pagination
39 p.
Report number
CONF-8810155--22

Conference

Title
16. water reactor safety information meeting.
Dates
24-27 Oct 1988.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20030191
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
AGING; BWR TYPE REACTORS; CHARPY TEST; EMBRITTLEMENT; EXPERIMENTAL DATA; LIFETIME; MECHANICAL PROPERTIES; PWR TYPE REACTORS; STAINLESS STEELS; THERMAL DEGRADATION
Descriptors DEC
ALLOYS; CARBON ADDITIONS; DATA; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IMPACT TESTS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL TESTS; NUMERICAL DATA; POWER REACTORS; REACTORS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Portions of this document are illegible in microfiche products.