Embrittlement of cast stainless steels in LWR systems
Creators
- 1. Argonne National Lab., IL (USA). Materials and Components Technology Div.
Description
Mechanical property data from Charpy-impact and J-R curve tests are presented for several experimental and commercial heats, as well as for reactor-aged material of CF-3, CF-8, and CF-8M grades of cast stainless steel. The efrects of material variables on the embrittlement of cast stainless steels are evaluated. Chemical composition and ferrite morphology have a strong effect on the extent and kinetics of embrittlement. The data are analyzed to establish the mechanisms of embrittlement. Procedures and correlations for predicting the impact strength and fracture toughness of cast components during reactor service are described. The lower-bound values of impact strength and fracture toughness for low-temperature aged cast stainless steel are defined. (orig.)
Availability note (English)
Available from Stuttgart Univ. (Germany, F.R.). Staatliche Materialpruefungsanstalt.Additional details
Additional titles
- Original title (no language)
- Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt 'Langzeitintegritaet der druckfuehrenden Bauteile von Kernkraftwerken'. Bd. 1 und 2.
Publishing Information
- Imprint Title
- Safety and reliability of plant technology with special emphasis on long-term integrity of pressure components of nuclear power plants. Vol. 1 and 2
- Imprint Pagination
- 784 p.
- Journal Page Range
- p. 12.1-12.23.
Conference
- Title
- Nuclear technology - long-term integrity of pressure components of nuclear power plants.
- Original Conference Title
- 15. MPA-Seminar ueber Sicherheit und Verfuegbarkeit in der Anlagentechnik: Kerntechnik - Langzeitintegritaet der Druckfuehrenden Bauteile von Kernkraftwerken
- Acronym
- 15. MPA-seminar on safety and reliability of plant technology
- Dates
- 5-6 Oct 1989.
- Place
- Stuttgart (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 21052344
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CASTINGS; CHARPY TEST; EMBRITTLEMENT; MECHANICAL PROPERTIES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL TESTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31-109-ENG-38
- Notes
- Imprint:Published in 2 separate volumes.;Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt 'Langzeitintegritaet der druckfuehrenden Bauteile von Kernkraftwerken'. Bd. 1 und 2.;Bd. 1: Behaelter- und Komponenten-Integritaet, strahleninduzierte Versproedung, zerstoerungsfreie Pruefung. Bd. 2: Zeitstandverhalten/Kriechvorgaenge, Rohrleitungsverhalten, Bruchmechanik.