Published March 2000 | Version v1
Report

Ultra-high temperature strength properties on Mod.9Cr-1Mo steel

  • 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

Description

A sodium-water reaction drove from the single tube break in steam generator of FBR might overheat labor tubes rapidly under internal pressure loadings. If the temperature of tube wall becomes too high, it has to be evaluated that the stress of tube does not exceed the material strength limit to prevent the propagation of tube rupture. This study clarified the tensile and creep properties of Mod.9Cr-1Mo steel at ultra-high temperature which will be used in evaluation of the tube burst by sodium-water reaction. The strain rates for tensile test are from 10%/min to 10%/sec, and creep-rupture time is maximum 277sec. The range of test temperature is 700degC to 1300degC. The main results obtained were as follows; (1) The evaluation data on the relationship between tensile strength and strain rate and creep-rupture strength in shorter time on Mod.9Cr-1Mo steel were acquired. (2) Short-term mechanical properties of Mod.9Cr-1Mo steel were evaluated based on the results of tensile and creep-rupture tests up to 1300degC. As a result of the evaluation, recommended equation of creep-rupture strength in the short-term was proposed. (3) Tensile and creep-rupture strength of Mod.9Cr-1Mo steel tube showed the value which was higher than the 2·1/4Cr-1Mo steel, and it was proven to have the superior properties. (author)

Availability note (English)

Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-2210, JICST Service Homepage: www.jst.go.jp/EN/JICST/ServiceGuide

Additional details

Publishing Information

Imprint Pagination
120 p.
Report number
JNC-TN--9400-2000-042

Optional Information

Notes
7 refs., 40 figs., 2 tabs.