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

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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 94
Creep-Fatigue Materials Database • Creation of a materials database for creep-fatigue performance Full C-F Model 1Cr0.5Mo (P12) 1.25Cr0.5Mo (P11) 2.25Cr1Mo (P22) 0.5Cr0.5Mo0.25V (CMV) 1Cr1Mo0.25V (CMV) 1.25Cr1Mo0.25V (CMV) P9 X10CrMoVNb (P91) 9Cr0.5Mo1.8WVNbB (P92) AISI 304 AISI 316 25Cr35NiNbMa (HK40) X20CrMoV12-1 7-9Cr2WV P23 Hastelloy XR Fe0.75Ni0.5MoCrV Fe2.25Cr1Mo0.25V Under Development Overview of ANSTO R&D Activities 13th Meeting of the Materials Project Management Board for the GIF VHTR System 95
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Australian’s Molten Salt Reactor
Page 3 and 4:
Uranium in Australia • Has the wo
Page 5 and 6:
ANSTO Australian Nuclear Science an
Page 7 and 8:
New ANSTO Research Structure ANSTO
Page 9 and 10:
Australian key capability overview
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Molten Salt Reactor (MSR) Material
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ANSTO/SINAP TMSR Research Program
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SINAP - ANSTO Material Development
Page 17 and 18:
SINAP Materials • Development of
Page 19 and 20:
SINAP NiMo-SiC Alloy C. Yang, O. Mu
Page 21 and 22:
Material Testing in Extreme Environ
Page 23:
ANSTO Material Testing • Irradiat
Page 26 and 27:
Samples Currently in OPAL (or Plann
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Ion Irradiation at ANSTO • 1MV VE
Page 30 and 31:
In-site 1MeV Kr + ion irradiation a
Page 32 and 33:
In situ micro tensile testing of He
Page 34 and 35:
Page 36 and 37:
SINAP GH3535 vs Hastelloy N Dorn-Sh
Page 38 and 39:
ANSTO Corrosion Testing • ANSTO-S
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Page 42 and 43:
SINAP GH3535: Irradiation & Corrosi
Page 44 and 45: ANSTO Material Testing • Irradiat
Page 46 and 47: SINAP GH 3535 Creep Testing in Molt
Page 48 and 49: SINAP GH 3535 Weld Characterisation
Page 50 and 51: Prediction of Weld Residual Stress
Page 52 and 53: Material Properties Comparison of t
Page 54 and 55: Prediction of Weld Residual Stress
Page 56 and 57: High Temperature Irradiation (Plann
Page 58 and 59: Effect of water ingress • Vibrati
Page 60 and 61: FE Model - Thermo-Mechanical Analys
Page 62 and 63: WRS - FE Modelling Y X Z D Plane 04
Page 64 and 65: ND Measurement 150 mm (X) 200 mm (Y
Page 66 and 67: WRS - Modelling & Measurement Somet
Page 68 and 69: WRS - Modelling & Measurement D2 Li
Page 70 and 71: Admiral Hyman Rickover (US Navy) An
Page 72 and 73: Admiral Hyman Rickover (US Navy)
Page 74 and 75: 74
Page 76 and 77: ANSTO and Generation IV Structural
Page 78 and 79: Radiation Damage Test Environments
Page 80 and 81: Specimens for Neutron Irradiation
Page 82 and 83: Active Sample Machining and Testing
Page 84 and 85: Single Crystal Ni, He+ Ion Irradiat
Page 86 and 87: Trends in Irradiation Strengthening
Page 88 and 89: Variation in Radiation Damage Morph
Page 90 and 91: Creep Rupture Assessment • Member
Page 92 and 93: Quantification of Accumulated Creep
Page 98 and 99: Salt Infiltration into Graphite Sal
Page 100 and 101: Combined Effects of Corrosion and I
Page 106 and 107: Additional Considerations: Welding
Page 108 and 109: Process Simulation: DMW Overview of
Page 110 and 111: ANSTO-University of Manchester RCA
Page 112: Conclusions • Variety of structur
Page 115 and 116: ANSTO Nuclear Medicine Project •
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Australian’s Molten Salt Reactor (MSR) Material Research Ondrej Muránsky

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