Development of elevated temperature structural design guide for Japanese demonstration breeder reactor

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Progress Report for Work Through September 2003, 2nd Annual/8th Quarterly Report

“…Even if an effective thermal sleeve is designed to isolate the outlet nozzle, it is undesirable to make a sudden transition from low to high temperature between the outlet nozzle and this piping because of the thermal stress induced at the transition. Although the circumstances are different, this has been an issue in fast breeder reactor development [Takakura 1995], where the temperatures involved are slightly higher than those in the SCWR (550 C in the FBR vs 500 C in the SCWR) but the net Von Mises stresses are much lower.…”

Update and Improve Subsection NH ?? Alternative Simplified Creep-Fatigue Design Methods

“…K ≤ q n /( q n -1) (3.5.6) Equation Based on a series of analytical studies reported by reference [15] and [16], the DDS incorporates a maximum global follow-up factor, q n = 3.0. Substituting Eq.…”