Australian’s Molten Salt Reactor (MSR) Material Research Ondrej Muránsky

P91 Japan Sodium-Cooled Fast Reactor Tubesheet
• Hot transient sodium temp = 600 C (2hr dwell)
• Cold transient temp = 250 C (1 hr hold)
• Rate Change = 5 C/s
• Cycle length = 3 h and 140s per cycle
• Number of test cycles = 1873
• Crack initiation mode creep-fatigue
• Maximum Crack Length = 3.7 mm
Ando (2014)
Original JAEA analyses performed using RCC-MR
time fraction (TF) models for P91. Strain ranges
derived using: (i) Stress Redistribution Locus, SRL;
(ii) Simple Elastic Follow-Up, SEF; and (iii) direct
inelastic implementation using FEA. ANSTO-EDF
Energy analyses (in red) used inelastic strain range
with ductility exhaustion models.
Overview of ANSTO R&D Activities
13th Meeting of the Materials Project Management Board for the GIF VHTR System
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