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

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SINAP GH3535: Irradiation & Corrosion As-Received Irradiated, No Corrosion Corrosion, No Radiation Irradiated + Corrosion • GH3535 alloy, FLiNaK salt, 10 17 ions/cm 2 He+ • Helium ion irradiation increases the thickness of the corrosion layer in the irradiated and corroded sample to more 30 times than in the un-irradiated sample. H. Zhu et al. High-temperature corrosion of helium ion-irradiated Ni-based alloy in fluoride molten salt Corrosion Science, 2015, 91, pp. 1-6.
SINAP Graphite: Irradiation & Corrosion Graphite, FLiNaK salt, 10 17 ions/cm 2 He+ As-Received Irradiated, No Corrosion Corrosion, No Radiation Irradiated + Corrosion • Un-irradiated • Irradiated • Graphite test coupons were irradiated with 30 keV He+ ions • One section was masked to prevent radiation damage • The samples exposed to molten FLiNaK salt (150h@750 ºC). • Clear variations in the corroded structures are visible • NEXAFS suggests Fluorination of surface Damaged Masked
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 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 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:
Page 104 and 105:
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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