Long-term creep rupture behavior of smoothed and notched bar specimens of low-carbon nitrogen-controlled 316 stainless steel (316FR) and their evaluation
- 1. Central Research Institute of Electric Power Industry (Japan)
- 2. Japan Atomic Power Company (Japan)
Description
Low-carbon, nitrogen-controlled 316 stainless steel is regarded as a principal candidate for a main structural material of future fast breeder reactor plants in Japan. To grasp creep deformation and rupture behavior of this steel whose modeling is indispensable in the design of high-temperature components, a number of uniaxial tensile creep tests have been conducted for four products of this steel at 550 oC and higher temperatures. Long-term creep rupture data up to about 94,000 h were obtained and used to examine the applicability of rupture and deformation estimation methods developed earlier. In addition, two tests were conducted using round-bar specimens with circumferential notches to make investigation of the effect of stress multiaxiality on creep damage
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2006.09.010Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2006.09.010;
- PII
- S0029-5493(06)00532-2;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 2
- Journal Page Range
- p. 310-321
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39049061
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CARBON; CREEP; DAMAGE; DEFORMATION; DESIGN; EVALUATION; FBR TYPE REACTORS; NITROGEN; NOTCHES; RUPTURES; SIMULATION; STAINLESS STEELS; STRESSES; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; ELEMENTS; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NONMETALS; REACTORS; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.