Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

Assessment of Creep Damage Evaluation Methods for Grade 91 Steel in the ASME and JSME Nuclear Codes

Jun 28, 2017, 5:50 PM
1h 10m
Yekaterinburg

Yekaterinburg

POSTER Track 2. Fast Reactor Operation and Decommissioning Poster Session 2

Speaker

Dr Tai Asayama (Japan Atomic Energy Agency)

Description

Grade 91 steel is a Code-approved construction material in the ASME and JSME nuclear codes. Applications of Grade 91 steel include intermediate heat exchanger, piping, steam generator tubing and shell, etc. for sodium fast reactor systems. Current creep-fatigue damage evaluation method in the ASME and JSME nuclear code differs in the method to calculate creep damage. In the simplified inelastic approach of the ASME Code, the creep damage is calculated using the isochronous stress-strain curves. In the JSME Code, the creep damage is evaluated using a creep strain equation combined with the strain hardening formulation. In this paper, these two approaches will be reviewed and creep damage predictions from illustrative examples using these two approaches will be presented. Approaches to possible harmonization will be discussed.

Country/Int. Organization

USA/Argonne National Laboratory

Primary author

Dr Ting-Leung Sham (Argonne National Laboratory)

Co-author

Dr Tai Asayama (Japan Atomic Energy Agency)

Presentation materials