Long-term embrittlement of cast duplex stainless steels in LWR systems
Creators
- 1. Argonne National Lab., IL (USA)
Description
This progress report summarizes work performed by Argonne National Laboratory on longterm thermal embrittlement of cast duplex stainless steels in LWR systems during the six months from October 1989 to March 1990. The results from Charpy-impact tests and microhardness measurements of the ferrite phase for several heats of cast stainless steel aged up to 30,000 h at 290--400 degree C are analyzed to establish the kinetics of thermal embrittlement. Correlations are presented for predicting the extent and kinetics of thermal embrittlement of cast stainless steels from material information that can be determined from the certified material test record. The extent of embrittlement is characterized by the room-temperature ''normalized'' Charpy-impact energy. Based on the information available, two methods are presented for estimating the extent of embrittlement at ''saturation,'' i.e., the minimum impact energy that would be achieved for the material after long-term aging. The first method utilizes only the chemical composition of the steel. The second method is used when metallographic information on the ferrite morphology, i.e., measured values of ferrite content and mean ferrite spacing of the steel, is also available. The change in Charpy-impact energy as a function of time and temperature of reactor service is then estimated from the extent of embrittlement at saturation and from the correlations describing the kinetics of embrittlement, which is expressed in terms of the chemical composition and aging behavior of the steel at 400 degree C. 37 refs., 16 figs., 4 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI91015982; NTIS; INIS; GPO.
Files
Additional details
Additional titles
- Subtitle (English)
- Semiannual report, October 1989--March 1990: Volume 5, No. 1
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- NUREG/CR--4744-Vol.5-No.1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23000431
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CHARPY TEST; CHEMICAL COMPOSITION; EMBRITTLEMENT; PROGRESS REPORT; PWR TYPE REACTORS; REACTOR COMPONENTS; STAINLESS STEELS; THERMAL DEGRADATION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL TESTS; POWER REACTORS; REACTORS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- ANL--91/7.