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

More documents

Recommendations

Info

In situ micro tensile testing of He +2 ion irradiated and implanted single crystal nickel film. Acta <strong>Material</strong>ia, 2015, 100, pp. 147-154. Micromechanical Tensile Testing Radiation direction
Trends in Radiation Strengthening with Dose • Ion irradiation provides useful qualitative information • Full-sample performance does not explicitly consider localised damage In situ micro tensile testing of He +2 ion irradiated and implanted single crystal nickel film. Acta <strong>Material</strong>ia, 2015, 100, pp. 147-154.
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 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 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 •
show all

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

Create successful ePaper yourself

Delete template?

Save as template?