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

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Additional Considerations: Welding • Understanding of microstructure and stress state around single- and multi-pass welded joints • Heavily involved in international round-robin programmes designed to identify best practise for joint characterisation and process simulation – NeT (AISI 316, Inconel 600, A508) – USNRC (DMW) • ANSTO carries out materials testing for materials data set required for simulation, as well as characterisation and performance evaluation of welded joints Overview of ANSTO R&D Activities 13th Meeting of the Materials Project Management Board for the GIF VHTR System 106
Material Test Data (High-Temperature LCF) Overview of ANSTO R&D Activities 13th Meeting of the Materials Project Management Board for the GIF VHTR System 107
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Australian’s Molten Salt Reactor
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Uranium in Australia • Has the wo
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ANSTO Australian Nuclear Science an
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New ANSTO Research Structure ANSTO
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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
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SINAP Materials • Development of
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SINAP NiMo-SiC Alloy C. Yang, O. Mu
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Material Testing in Extreme Environ
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ANSTO Material Testing • Irradiat
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Samples Currently in OPAL (or Plann
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Ion Irradiation at ANSTO • 1MV VE
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In-site 1MeV Kr + ion irradiation a
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In situ micro tensile testing of He
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Page 36 and 37:
SINAP GH3535 vs Hastelloy N Dorn-Sh
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ANSTO Corrosion Testing • ANSTO-S
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Page 42 and 43:
SINAP GH3535: Irradiation & Corrosi
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Page 46 and 47:
SINAP GH 3535 Creep Testing in Molt
Page 48 and 49:
SINAP GH 3535 Weld Characterisation
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Prediction of Weld Residual Stress
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Material Properties Comparison of t
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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 98 and 99: Salt Infiltration into Graphite Sal
Page 100 and 101: Combined Effects of Corrosion and I
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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