High temperature design curves for high nitrogen grades of 316LN stainless steel

Nuclear Engineering and Design

Volumn 240, Issue 6, 2010, Pages 1363-1370

  Ganesh Kumar, J ^a   Chowdary, M ^b   Ganesan, V ^a   Paretkar, R K ^b   Bhanu Sankara Rao, K ^c   Mathew, M D ^a  

^a INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH   (India)

^b VISVESVARAYA NATIONAL INSTITUTE OF TECHNOLOGY   (India)

^c UNIVERSITY OF HYDERABAD   (India)

Author keywords

[No Author keywords available]

Indexed keywords

316L; CREEP DATA; CREEP PROPERTIES; CREEP STRENGTHS; CREEP TESTS; DESIGN CURVES; DESIGN LIFE; HIGH TEMPERATURE; HIGH TEMPERATURE DESIGN; HIGH TEMPERATURE MECHANICAL PROPERTIES; HIGH-NITROGEN; LOW CARBON; NITROGEN CONTENT; NUCLEAR CODES; ROOM TEMPERATURE; RUPTURE LIFE; SODIUM COOLED FAST REACTOR; STRESS LEVELS; STRUCTURAL COMPONENT; STRUCTURAL MATERIALS; TENSILE TESTS;

BUILDING MATERIALS; CREEP; DESIGN; DISKS (STRUCTURAL COMPONENTS); FAST REACTORS; LOW CARBON STEEL; MECHANICAL PROPERTIES; NITROGEN; SODIUM; TENSILE STRENGTH; TENSILE TESTING;

STAINLESS STEEL;

EID: 77950919425     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.02.038     Document Type: Article

References (10)

1. Ganesan V., Mathew M.D., and Bhanu Sankara Rao K. Influence of nitrogen on tensile properties of 316LN SS. Mater. Sci. Technol. 25 5 (2009) 614-618
2. Ganesan, V., Mathew, M.D., Bhanu Sankara Rao, K., 2010. Creep strengthening of low carbon grade type 316 stainless steel by nitrogen. Trans. Indian Inst. Met., in press.
3. Mannan S.L., Chetal S.C., Baldev Raj, and Bhoje S.B. Selection of materials for prototype fast breeder reactor. Trans. Indian Inst. Met. 56 2 (2003) 155-178
4. Matera R. High temperature time dependent allowable stress and isochronous curves of an Austenitic Mn-Cr steel. J. Nucl. Mater. 155 (1988) 639-643
5. Nickel H., Schubert F., Penkalla H.J., and Breitbach G. Aspects of design codes for metallic high temperature components. Int. J. Pressure Vessels Piping 47 (1991) 167-192
6. RCC-MR, 2007. Design and construction rules for mechanical components of nuclear installations, Section 1, subsection. Z. AFCEN, Paris.
7. Roche R.L. French administrative practice and design codes for nuclear vessels. Nucl. Eng. Des. 129 (1991) 231-238
8. Tavassoli A.A.F. Materials design data for fusion reactors. J. Nucl. Mater. 258 (1998) 85-96
9. Tavassoli A.A., and Touboul F. Austenitic stainless steels, status of the properties database and design rule development. J. Nucl. Mater. 233 (1996) 51-61
10. Tavassoli A.A.F., Rensman J.W., Schirra M., and Shiba K. Materials design data for reduced activation martensitic steel type F82H. Fusion Eng. Des. 61 (2002) 617-628