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

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Prediction of Weld Residual Stress - ANSTO has developed complex models of microstructure and stress state around multi-pass welded joints - Used to support plant maintenance and design decisions NeT TG6 three-pass Inconel 82 slot-weld in an Inconel 600 (international benchmark specimen). The Abaqus half model depicting the basic plate geometry and three consecutive passes filling the slot. The insert shows in detail elements associated with passes 1 to 3. 76 mm (Z) 200 mm (Z) 150 mm (X)
Thermal Analysis PASS.3 PASS.2 PASS.1 Welding Direction 1380C Isotherm Weld Metal Parent Metal
Page 1 and 2: 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
Page 11 and 12: Molten Salt Reactor (MSR) Material
Page 13 and 14: ANSTO/SINAP TMSR Research Program
Page 15 and 16: 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
Page 28 and 29: 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: ANSTO Material Testing • Irradiat
Page 36 and 37: SINAP GH3535 vs Hastelloy N Dorn-Sh
Page 38 and 39: ANSTO Corrosion Testing • ANSTO-S
Page 42 and 43: SINAP GH3535: Irradiation & Corrosi
Page 46 and 47: SINAP GH 3535 Creep Testing in Molt
Page 48 and 49: SINAP GH 3535 Weld Characterisation
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 94 and 95: P91 Japan Sodium-Cooled Fast Reacto
Page 96 and 97: ANSTO and Generation IV Structural
Page 98 and 99: Salt Infiltration into Graphite Sal
Page 100 and 101:
Combined Effects of Corrosion and I
Page 102 and 103:
ANSTO and Generation IV Structural
Page 104 and 105:
ANSTO and Generation IV Structural
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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