Australian’s Molten Salt Reactor (MSR) Material Research Ondrej Muránsky
11_Ondrej_Muransky 11_Ondrej_Muransky
Australian’s Molten Salt Reactor (MSR) Material Research Ondrej Muránsky
- Page 2 and 3: Australia’s Resources
- Page 4 and 5: • Carbonatite, Placer depositions
- Page 6 and 7: Australian’s Nuclear Lab for 50 Y
- Page 8 and 9: Australia and the Gen IV Internatio
- Page 10 and 11: Australia’s GIF Research Followin
- Page 12 and 13: ANSTO: Nuclear Fuel Cycle R&D • F
- Page 14 and 15: ANSTO/SINAP TMSR Research Program
- Page 16 and 17: SINAP Material Development - Proper
- Page 18 and 19: SINAP NiMo-SiC Alloy SiC SiC Ni 3 S
- Page 20 and 21: SINAP NiMo-SiC Alloy Intensity [au]
- Page 22 and 23: ANSTO Material Testing • Irradiat
- Page 25 and 26: Neutron Irradiation Specimens • M
- Page 27 and 28: Active Sample Machining and Testing
- Page 29 and 30: Single Crystal Ni, He+ Ion Irradiat
- Page 31 and 32: Dislocation Structure • In-situ 1
- Page 33 and 34: Trends in Radiation Strengthening w
- Page 35 and 36: SINAP GH3535 vs Hastelloy N Larson
- Page 37 and 38: ANSTO Material Testing • Irradiat
- Page 39 and 40: Corrosion/Salt Infiltration into Gr
- Page 41 and 42: SINAP GH3535: Irradiation & Corrosi
- Page 43 and 44: SINAP Graphite: Irradiation & Corro
- Page 45 and 46: SINAP GH 3535 Creep Testing in Molt
- Page 47 and 48: SINAP GH 3535 Creep Testing in Molt
- Page 49 and 50: ANSTO’s Numerical Weld Modelling
- Page 51 and 52: Thermal Analysis PASS.3 PASS.2 PASS
<strong>Australian’s</strong> <strong>Molten</strong> <strong>Salt</strong> <strong>Reactor</strong> (<strong>MSR</strong>)<br />
<strong>Material</strong> <strong>Research</strong><br />
<strong>Ondrej</strong> <strong>Muránsky</strong>
Australia’s Resources
Uranium in Australia<br />
• Has the world’s largest<br />
reserves of uranium<br />
(23% of the world total)<br />
• Is the world's thirdranking<br />
producer behind<br />
Kazakhstan and Canada<br />
• In 2012, produced over<br />
7000 tonnes of uranium<br />
oxide concentrate<br />
(U 3 O 8 )<br />
• Exports to countries who<br />
have signed the Nuclear<br />
Non-Proliferation Treaty.<br />
Source: Geoscience Australia
• Carbonatite, Placer<br />
depositions, Vin-type<br />
deposits, Alkaline rocks:<br />
World resources: ~ 6 mil<br />
tons.<br />
• Australian Thorium<br />
resources estimate ~0.5<br />
mil tons.<br />
• ~ 8.8% of total world<br />
resources<br />
• No current production of<br />
thorium in Australia<br />
Thorium in Australia<br />
Source: Geoscience Australia
ANSTO<br />
Australian Nuclear Science and<br />
Technology Organisation
<strong>Australian’s</strong> Nuclear Lab for 50 Years<br />
AAEC<br />
1952 - 1987<br />
ANSTO<br />
1987 - Today
New ANSTO <strong>Research</strong> Structure<br />
ANSTO Gen IV and <strong>MSR</strong> <strong>Research</strong><br />
7
Australia and the Gen IV International Forum<br />
• In 2015, the Australia Federal<br />
Government petitioned to join the<br />
Generation IV International Forum<br />
• Petition presented to GIF Policy<br />
Group in Oct 2015<br />
• GIF Policy Group Delegation Visit to<br />
Sydney in Feb 2016<br />
• GIF Policy Group unanimously<br />
endorsed Australian membership in<br />
April, 2016<br />
• ANSTO signed the GIF Charter in<br />
June 2016 initiating Australia’s<br />
membership into the Forum<br />
GIF Policy Group Delegation to<br />
Australia, 2-4 February 2016<br />
Prof Lyndon Edwards, former<br />
Head, Institute of <strong>Material</strong>s Engineering now<br />
National Director, Australian Generation IV<br />
International Forum <strong>Research</strong>
Australian key capability overview<br />
• <strong>Reactor</strong> risk and safety analysis<br />
• Radiation damage<br />
• Creep, creep fatigue and code development<br />
• <strong>Molten</strong> salt corrosion and testing<br />
• Atomistic and molecular modelling<br />
• Structural Integrity and weld modelling<br />
Also some expertise on GIF relevant:<br />
• Education and Training<br />
• Economic Modelling (principally from UNSW)
Australia’s GIF <strong>Research</strong><br />
Following its success in gaining membership of GIF, Australia is<br />
proposing to join:<br />
• The Very High Temp <strong>Reactor</strong> (VHTR) SA<br />
• The <strong>Molten</strong> <strong>Salt</strong> <strong>Reactor</strong> (<strong>MSR</strong>) pSSC<br />
• The VHTR <strong>Material</strong> (MAT) PA<br />
• The Risk and Safety Working Group.<br />
In addition, with our University partners we are exploring how we<br />
might make contributions to:<br />
• The GIF Education and Training Working Group<br />
• The Economic Modelling Working Group<br />
SA - System Arrangements<br />
pSSC - Provisional System Steering Committee<br />
PA - Project Arrangements
<strong>Molten</strong> <strong>Salt</strong> <strong>Reactor</strong> (<strong>MSR</strong>)<br />
<strong>Material</strong> <strong>Research</strong>
ANSTO: Nuclear Fuel Cycle R&D<br />
• Fuel/cladding interactions<br />
– Use of atomistic modelling (e.g. DFT)<br />
• Structural materials performance under extreme<br />
conditions<br />
– Irradiation, corrosion, high temperatures and/or deformation<br />
• Separation science<br />
– Synthesis and analysis of titania frameworks for separation of U, Pu<br />
• Wasteform fabrication<br />
– Construction of a Synroc waste treatment plant to reduce volume of ANSTO<br />
nuclear by-products by 99%
ANSTO/SINAP T<strong>MSR</strong> <strong>Research</strong> Program<br />
• Shanghai Institute of Applied Physics<br />
(SINAP), Chinese Academy of<br />
Science (CAS)<br />
– Centre for Thorium <strong>Molten</strong> <strong>Salt</strong><br />
<strong>Reactor</strong> (T<strong>MSR</strong>) systems<br />
• Australia/China Science and<br />
<strong>Research</strong> Fund Grant 2013-2015<br />
• ANSTO-SINAP Joint <strong>Material</strong>s<br />
<strong>Research</strong> Centre<br />
– <strong>Material</strong>s technology for <strong>Molten</strong> <strong>Salt</strong><br />
<strong>Reactor</strong>s<br />
• <strong>Molten</strong> salt corrosion<br />
• Radiation damage<br />
• High temperature behaviour
ANSTO/SINAP T<strong>MSR</strong> <strong>Research</strong> Program<br />
• Shanghai Institute of Applied Physics<br />
(SINAP), Chinese Academy of<br />
Science (CAS)<br />
– Centre for Thorium <strong>Molten</strong> <strong>Salt</strong><br />
<strong>Reactor</strong> (T<strong>MSR</strong>) systems<br />
• Australia/China Science and<br />
<strong>Research</strong> Fund Grant 2013-2015<br />
• ANSTO-SINAP Joint <strong>Material</strong>s<br />
<strong>Research</strong> Centre<br />
– <strong>Material</strong>s technology for <strong>Molten</strong> <strong>Salt</strong><br />
<strong>Reactor</strong>s<br />
• <strong>Molten</strong> salt corrosion<br />
• Radiation damage<br />
• High temperature behaviour
SINAP - ANSTO<br />
<strong>Material</strong> Development
SINAP <strong>Material</strong> Development<br />
- Property of Hastelloy N:<br />
- Very good corrosion resistance to molten salt<br />
- Operated successfully in <strong>MSR</strong>E more than four years<br />
- Still the best choice for the <strong>MSR</strong> structural material<br />
- Only 704℃<br />
- Helium embrittlement<br />
Chao Yang, PhD<br />
Candidate,<br />
Prof. Xingtai Zhou<br />
12 months stay at<br />
ANSTO<br />
High-temperature<br />
strength<br />
Corrosion<br />
resistance<br />
Irradiation<br />
resistance<br />
Development of Ni-SiC and NiMo-SiC<br />
dispersion precipitation strengthened<br />
(DPS) alloys for future T<strong>MSR</strong> systems.<br />
Advantages of SiC: Ceramic material,<br />
Irradiation resistance, Corrosion<br />
resistance, High temperature stability<br />
F/M/A steel<br />
ODS steel<br />
Hastelloy N<br />
GH3535<br />
ODS alloy<br />
Ceramics<br />
- ODS nickel alloys(weak corrosion resistance )<br />
- Ceramics & ceramic matrix composites(lack of connection<br />
technology )
SINAP <strong>Material</strong>s<br />
• Development of new materials for molten salt reactor<br />
systems environments (high-temperature, corrosion,<br />
radiation)<br />
SINAP <strong>Material</strong>s:<br />
1. Ni-SiC, Ni-16Mo-SiC<br />
2. GH3535, a Chinese variant of Hastelloy N with<br />
the nominal composition of Ni–16Mo–7Cr–4Fe<br />
and Si used as an O getter<br />
3. Various Grades of Nuclear Graphite.
SINAP NiMo-SiC Alloy<br />
SiC<br />
SiC<br />
Ni 3 Si<br />
• SiC – dispersion strengthening<br />
• Ni 3 Si – precipitation strengthening<br />
• Mo 2 C – grain refinement, degradation of elongation<br />
C. Yang, O. Muransky, H. Zhu, G.J. Thorogood, H. Huang, X. Zhou, On the origin of strengthening mechanics in Ni-Mo alloys<br />
prepared via powder metallurgy, <strong>Material</strong>s and Design, DOI:10.1016/j.matdes.2016.10.024.
SINAP NiMo-SiC Alloy<br />
C. Yang, O. Muransky, H. Zhu, G.J. Thorogood, H. Huang, X. Zhou, On the origin of strengthening mechanics in Ni-Mo alloys<br />
prepared via powder metallurgy, <strong>Material</strong>s and Design, DOI:10.1016/j.matdes.2016.10.024.
SINAP NiMo-SiC Alloy<br />
Intensity [au]<br />
Lattice Spacing [A]<br />
C. Yang, O. Muransky, H. Zhu, G.J. Thorogood, H. Huang, X. Zhou, On the origin of strengthening mechanics in Ni-Mo alloys<br />
prepared via powder metallurgy, <strong>Material</strong>s and Design, DOI:10.1016/j.matdes.2016.10.024.
<strong>Material</strong> Testing in Extreme<br />
Environments
ANSTO <strong>Material</strong> Testing<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature creep
ANSTO <strong>Material</strong> Testing<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature creep
Neutron Irradiation Specimens<br />
• Miniature dog-bone samples<br />
• Small punch discs<br />
• Compact tension discs<br />
• Quarter-size Charpy samples<br />
• Corrosion samples<br />
1 dpa/yr
Samples Currently in OPAL (or Planned for Insertion)<br />
<strong>Material</strong> Sample type Irradiation time Source<br />
MA957 TEM discs 460 days IME/ORNL i<br />
CLAM “ “ IME i<br />
TiAl FT “ “ IME/LANL ii<br />
AlMg5 Mini tensile “ IME/OPAL Surveillance iv<br />
Zr-3.5Sn “ 460 days IME/Queens ii<br />
TiAl DP TEM discs 460 days IME/LANL ii<br />
Ti-6Al-4V “ “ IME i<br />
Zr-2.5Nb “ “ IME i<br />
Zr-4 CT 460 days OPAL Surveillance iv<br />
Zr-4 CT 5 years OPAL Surveillance iv<br />
Zr-4 CT 10 years OPAL Surveillance iv<br />
NiCrMoFe Small Punch 460 days IME/SINAP JRC iii<br />
NiCrMoFe “ 920 days IME/SINAP JRC iii<br />
Ti45Al “ 460 days IME i<br />
Ti45Al2Nb “ “ IME i<br />
Ti45Al TEM disc “ IME i<br />
Ti45Al2Nb “ “ IME i<br />
Zr-2.5Nb “ “ IME/OPAL i<br />
NiCrMoFe “ “ IME/SINAP JRC iii<br />
Zr-3.5Sn Mini Tensile 5 years IME/Queens ii<br />
NiCrMoFe “ 460 days IME/SINAP JRC iii<br />
Al6061 “ 5 years OPAL Surveillance iv<br />
i<br />
Internal research<br />
ii<br />
unfunded collaborative research<br />
iii<br />
partially funded research with external partners<br />
iv<br />
OPAL <strong>Material</strong>s Surveillance Program (MSP)<br />
• Zr and Al alloys<br />
– Predominantly for OPAL support<br />
• Titanium Aluminides<br />
– Internal research<br />
• Ni alloys<br />
– Collaborative work (SINAP <strong>MSR</strong>)<br />
• Additional planned materials<br />
– A508 (PM, WM, HIP)<br />
– ODS<br />
– Graphite<br />
– Tungsten<br />
26
Active Sample Machining and Testing<br />
• Active samples sent to MEHC, which contains:<br />
– Mechanical testing facilities for active material<br />
– Micromachining facilities to allow samples to exit cells<br />
• MEHC currently in licensing/commissioning stage<br />
27
Ion Irradiation at ANSTO<br />
• 1MV VEGA accelerator<br />
• 2MV STAR tandetron accelerator<br />
• 6MV SIRIUS tandem accelerator<br />
• 10MV ANTARES tandem<br />
accelerator<br />
– Energies from < 1 MeV to 100<br />
MeV
Single Crystal Ni, He+ Ion Irradiation<br />
11.85 µm<br />
~ 19 dpa<br />
Irradiation<br />
direction<br />
Front surface<br />
(Entry surface)<br />
Back surface<br />
(Exit surface)<br />
~ 10 dpa<br />
SRIM (The Stopping and Range of Ions in Matter) estimates for He+ irradiation of Ni<br />
29
In-site 1MeV Kr + ion irradiation at RT & 450C<br />
Argonne National<br />
Laboratory Hitachi<br />
H9000NAR IVEM<br />
operated at 200 kV<br />
In-situ irradiation experiments were performed on TEM<br />
thinned (~ 100 nm) Ni-Mo-Cr-Fe alloys using 1 MeV Kr +<br />
ions at room temperature (25ᵒC) and 450ᵒC up to to 100<br />
dpa (1.77 x 10 18 ions/cm 2 ). [110] zone axis.<br />
M. Reyes et al., Microstructural Evolution of an Ion Irradiated Ni-Mo-Cr-Fe Alloy at Elevated Temperatures.<br />
<strong>Material</strong>s Transactions, 2014, 55, pp. 428-433.
Dislocation Structure<br />
• In-situ 1 MeV Kr + ion irradiation at<br />
450 o C<br />
• Post Facto TEM analysis<br />
• High densities of both faulted and unfaulted<br />
loops observed<br />
• Analysis shows they are un-faulted<br />
½〈110〉 SIA loops and faulted 1/3〈111〉<br />
vacancy Frank loops<br />
• MD simulations of defects near ½〈110〉<br />
edge dislocations suggests that<br />
redistribution of displaced atoms from<br />
the cascade region towards the<br />
dislocation core may result in<br />
dislocation climb so remaining<br />
vacancies may partially collapse and<br />
form 1/3〈111〉 faulted vacancy Frank<br />
loops nearby.<br />
b<br />
• Faulted Loop<br />
• Faulted Loop<br />
a<br />
• Un-Faulted Loop
In situ micro tensile testing of He +2 ion irradiated and implanted single crystal nickel film.<br />
Acta <strong>Material</strong>ia, 2015, 100, pp. 147-154.<br />
Micromechanical Tensile Testing<br />
Radiation direction
Trends in Radiation Strengthening with Dose<br />
• Ion irradiation provides useful qualitative information<br />
• Full-sample performance does not explicitly consider localised damage<br />
In situ micro tensile testing of He +2 ion irradiated and implanted single crystal nickel film.<br />
Acta <strong>Material</strong>ia, 2015, 100, pp. 147-154.
ANSTO <strong>Material</strong> Testing<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature
SINAP GH3535 vs Hastelloy N<br />
Larson Miller Parameter (LMP)<br />
LMP = T [log (t r ) + C]<br />
T - temperature ( o K)<br />
t r - time to rupture (hrs)<br />
C - constant (17.5)
SINAP GH3535 vs Hastelloy N<br />
Dorn-Shephard Parameter for 1% creep<br />
Log(1/ t 1%creep ) + Log(exp(42600/T)<br />
T - temperature ( o K)<br />
t 1%creep - time to 1% creep strain (hrs)<br />
Creep exponent<br />
n = 4
ANSTO <strong>Material</strong> Testing<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature
ANSTO Corrosion Testing<br />
• ANSTO-SINAP JRC (<strong>MSR</strong>)<br />
– FLiNaK salt composition<br />
– Tests conducted at 650ºC - 750ºC for<br />
10, 100 and 200 h<br />
• SINAP <strong>Material</strong>s<br />
– GR 3535, Graphite, NiMo-SiC,<br />
Hastelloy-N<br />
Hastelloy-N, Electron Back-Scatter Diffraction (EBSD) and<br />
Energy Dispersive Spectroscopy (EDS) chromium (Cr)<br />
distribution map, 200h/650C, FLiNaK.
Corrosion/<strong>Salt</strong> Infiltration into Graphite<br />
• <strong>Salt</strong> infiltration into various grades of graphite at<br />
different pressures (a) 1.0 atm; (b) 1.5 atm; (c) 3.0 atm;<br />
and (d) 5.0 atm.<br />
Z. He et al., <strong>Molten</strong> FLiNaK salt infiltration into degassed nuclear<br />
graphite under inert gas pressure, Carbon, 2015, 84, pp. 511-518.
ANSTO <strong>Material</strong> Testing<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature
SINAP GH3535: Irradiation & Corrosion<br />
GH3535: Vapour etch top figures, salt corrosion bottom figures<br />
H. Zhu et al. High-temperature corrosion of helium ion-irradiated Ni-based alloy in fluoride molten salt<br />
Corrosion Science, 2015, 91, pp. 1-6.
SINAP GH3535: Irradiation & Corrosion<br />
As-Received<br />
Irradiated, No Corrosion<br />
Corrosion, No Radiation<br />
Irradiated + Corrosion<br />
• GH3535 alloy, FLiNaK salt, 10 17 ions/cm 2 He+<br />
• Helium ion irradiation increases the thickness of the corrosion layer in the<br />
irradiated and corroded sample to more 30 times than in the un-irradiated sample.<br />
H. Zhu et al. High-temperature corrosion of helium ion-irradiated Ni-based alloy in fluoride molten salt<br />
Corrosion Science, 2015, 91, pp. 1-6.
SINAP Graphite: Irradiation & Corrosion<br />
Graphite, FLiNaK salt, 10 17 ions/cm 2 He+<br />
As-Received<br />
Irradiated, No Corrosion<br />
Corrosion, No Radiation<br />
Irradiated + Corrosion<br />
• Un-irradiated<br />
• Irradiated<br />
• Graphite test coupons were irradiated with 30 keV He+ ions<br />
• One section was masked to prevent radiation damage<br />
• The samples exposed to molten FLiNaK salt (150h@750 ºC).<br />
• Clear variations in the corroded structures are visible<br />
• NEXAFS suggests Fluorination of surface<br />
Damaged<br />
Masked
ANSTO <strong>Material</strong> Testing<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature creep<br />
– Irradiation under high temperature
SINAP GH 3535 Creep Testing in <strong>Molten</strong> <strong>Salt</strong><br />
GH3553 creep rupture test (190 MPa @ 700 ºC)<br />
Initial results show significant effect of salt on creep life
SINAP GH 3535 Creep Testing in <strong>Molten</strong> <strong>Salt</strong><br />
SEM Band contrast Cr Mo<br />
20 µm<br />
EDS chemical<br />
composition<br />
(Average wt%)<br />
Region Ni Mo Cr Fe Mn Si<br />
Bulk sample 71.1 16.3 7.3 4.1 0.7 0.5<br />
<strong>Salt</strong> affected regions (st dev) 82.8 (0.5) 12.1 (0.4) 1.5 (0.2) 3.2 (0.2) 0.2 (0) 0.1 (0)
SINAP GH 3535 Creep Testing in <strong>Molten</strong> <strong>Salt</strong><br />
SEM<br />
Euler Map<br />
Cr<br />
20 µm<br />
Evidence of preferential<br />
grain boundary attack
SINAP GH 3535 Weld Characterisation<br />
48
ANSTO’s Numerical Weld<br />
Modelling
Prediction of Weld Residual Stress<br />
- ANSTO has developed complex<br />
models of microstructure and<br />
stress state around multi-pass<br />
welded joints<br />
- Used to support plant<br />
maintenance and design<br />
decisions<br />
NeT TG6 three-pass Inconel 82 slot-weld in an Inconel<br />
600 (international benchmark specimen). The Abaqus<br />
half model depicting the basic plate geometry and three<br />
consecutive passes filling the slot. The insert shows in<br />
detail elements associated with passes 1 to 3.<br />
76 mm (Z)<br />
200 mm (Z)<br />
150 mm (X)
Thermal Analysis<br />
PASS.3<br />
PASS.2<br />
PASS.1<br />
Welding Direction<br />
1380C Isotherm<br />
Weld Metal<br />
Parent Metal
<strong>Material</strong> Properties<br />
Comparison of the room temperature cyclic responses of Inconel 600 (parent metal) and<br />
Inconel 82 (weld metal) predicted by mixed isotropic-kinematic hardening plasticity<br />
model when using the first and second cycle to derive mixed hardening parameters.
Prediction of Weld Residual Stress<br />
Z<br />
X<br />
- Weld Metal: Inconel 82<br />
- Parent Metal: Inconel 600<br />
- 3-Pass Slot weld<br />
D Plane
Prediction of Weld Residual Stress<br />
D2 Line<br />
D10 Line
Thank you
High Temperature Irradiation (Planned)<br />
• Motivation<br />
– Radiation damage is controlled by a thermally<br />
activated processes, so some temperature<br />
control is desirable<br />
• Planned Work<br />
– Neutronics/gamma heating calculations<br />
– Thermal hydraulics calculations (safety case)<br />
– Can design and T&C specifications<br />
Muroga (2001)<br />
OPAL contains empty space (“hot<br />
source”) in the RPV. By developing a<br />
suitable holder (such as the ORNL<br />
HFIR sample heating holder, left),<br />
samples may be irradiated in OPAL at<br />
higher temperatures, thereby enabling<br />
elevated-temperature damage mechanisms<br />
to be characterised.
Effect of water ingress<br />
• XRD shows the formation of hydroxide species in the salt<br />
– Potassium hydroxide, sodium hydroxide and hydrated versions of these<br />
• Solid state nuclear magnetic resonance spectroscopy (NMR)<br />
– Exploits magnetic properties of certain nuclei<br />
• Nuclei absorb electromagnetic radiation and signals shift based on bonding environment<br />
(hydrogen and fluorine are good nuclei – allows for quantitative determinations)<br />
• Hydroxide and other species measured by proton NMR, Fluorine NMR used to measure main<br />
slat components which show good agreement to the literature<br />
– Extra peaks associated with Na are due to higher resolution instrument and larger spectral window<br />
X-ray diffraction<br />
19<br />
F Solid-state nuclear magnetic<br />
resonance spectroscopy
Effect of water ingress<br />
• Vibrational spectroscopy allows the<br />
chemical speciation to be determined<br />
– Raman spectroscopy measures bond<br />
polarisation<br />
– Infrared measures dipole moments<br />
• Observe the formation of HF species<br />
in the salt<br />
– Associated with KF (extremely<br />
hygroscopic and deliquescent)
H 2 O Decomposition in Fluoride <strong>Salt</strong>s<br />
• Molecular dynamics using DFT used to study the stability of H 2 O in fluoride salts.<br />
• Deviation from stoichiometry found to break H 2 O into OH - and free H + (forming<br />
HF in hyper-stoichiometric salt).<br />
• Calculations carried out at 1000 K with a time step of 1 fs. (Run for 0.1 ns).<br />
• Phenomenon seen in non-stoichiometric F 2 LiNa and F 3 LiNaK.<br />
Stoichiometric F 3 LiNaK<br />
Non-Stoichiometric F 3 LiNaK
FE Model<br />
- Thermo-Mechanical<br />
Analysis<br />
- 3D Half Model<br />
- 407222 (HEX,<br />
Quadratic)<br />
- Thermal Analysis:<br />
DC3D20<br />
- Mechanical<br />
Analysis: C3D20R<br />
76 mm (Z)<br />
200 mm<br />
(Z)<br />
► NeT TG6 three-pass Inconel 82 slot-weld in<br />
an Inconel 600 (international benchmark<br />
specimen). The Abaqus half model depicting<br />
the basic plate geometry 01 and three<br />
150 mm (X)
<strong>Material</strong> Properties<br />
► Comparison of the room temperature cyclic responses of Inconel 600 (parent metal) and Inconel 82 (weld metal) predicted by<br />
mixed isotropic-kinematic hardening plasticity model when using the first and second cycle to derive mixed hardening<br />
parameters.<br />
02
WRS - FE Modelling<br />
Y<br />
X<br />
Z<br />
D Plane<br />
04
WRS - FE Modelling<br />
Y<br />
X<br />
Z<br />
B Plane<br />
04
ND Measurement<br />
150 mm (X)<br />
200 mm<br />
(Y)<br />
- Monochromator: bent Si single crystal<br />
- Monochromator angle: 33.52<br />
- Take-off angle: 66.98°<br />
- Detector angle: 88.0°<br />
- Wavelength: 1.498Å<br />
- Measured reflection: {311}<br />
- Primary slit: 2mm<br />
- Secondary slit: radial collimator<br />
- Gauge volume: 2x2x2mm 2<br />
ε 311 ij = d ij<br />
311 311<br />
− d 0,ij<br />
311<br />
d 0,ij<br />
Parent Metal<br />
Weld Metal<br />
σ 311 E 311<br />
ij =<br />
(1 + υ 311 ) ε ij +<br />
υ 311<br />
1 − 2υ 311 (ε 11<br />
311 + ε 311 22 + ε 311 33 )<br />
Big Grains in<br />
the Weld<br />
Region<br />
05
d0 Measurements<br />
06
WRS - Modelling & Measurement<br />
Something seems to be<br />
wrong here. It looks that<br />
for the transverse<br />
direction we are B2 using Line<br />
the d0 from the parent<br />
B6 Line<br />
metal, while for the<br />
longitudinal direction we<br />
seems to be using the<br />
d0 from the weld metal.<br />
Can you please double<br />
check this. Something is<br />
certainly not right,<br />
because the model<br />
agrees in one direction<br />
and disagree in another<br />
direction. It should<br />
behave consistently<br />
between transverse and<br />
longitudinal. Similar to<br />
lines B2 and B10.<br />
07
WRS - Modelling & Measurement<br />
B10 Line<br />
BD Line<br />
08
WRS - Modelling & Measurement<br />
D2 Line<br />
D5 Line<br />
09
WRS - Modelling & Measurement<br />
This doesn’t seem to be<br />
right. We are measuring<br />
lower stresses along<br />
D7.5 than along Line<br />
D10. And again the<br />
model agrees in two<br />
directions and disagree<br />
in one direction, that<br />
doesn’t seem to be right.<br />
For D7.5 line we should<br />
use the same d0s as for<br />
line D10. How did we get<br />
the d0s along the line<br />
D7.5 line? I don’t see a<br />
reason why it should be<br />
different from the D10.<br />
D7 Line<br />
D10 Line<br />
10
Admiral Hyman Rickover (US Navy)<br />
An academic reactor or reactor plant almost always<br />
has the following basic characteristics:<br />
(1) It is simple.<br />
(2) It is small.<br />
(3) It is cheap.<br />
(4) It is light.<br />
(5) It can be built very quickly.<br />
(6) It is very flexible in purpose.<br />
(7) Very little development will be required. It will<br />
use off-the-shelf components.<br />
(8) The reactor is in the study phase. It is not being<br />
built now.
Admiral Hyman Rickover (US Navy)<br />
On the other hand a practical reactor can be<br />
distinguished by the following characteristics:<br />
(1) It is being built now.<br />
(2) It is behind schedule.<br />
(3) It requires an immense amount of development<br />
on apparently trivial items.<br />
(4) It is very expensive.<br />
(5) It takes a long time to build because of its<br />
engineering development problems.<br />
(6) It is large.<br />
(7) It is heavy.<br />
(8) It is complicated.
Admiral Hyman Rickover (US Navy)<br />
• The tools of the academic designer are a piece of paper and a<br />
pencil with an eraser. If a mistake is made, it can always be<br />
erased and changed.<br />
• If the practical-reactor designer errs, he wears the mistake<br />
around his neck; it cannot be erased. Everyone sees it.<br />
• The academic-reactor designer is a dilettante. He has not had to<br />
assume any real responsibility in connection with his projects.<br />
He is free to luxuriate in elegant ideas, the practical<br />
shortcomings of which can be relegated to the category of "mere<br />
technical details.”<br />
• The practical-reactor designer must live with these same<br />
technical details. Although recalcitrant and awkward, they must<br />
be solved and cannot be put off until tomorrow. Their solution<br />
requires manpower, time and money.<br />
In Nuclear, materials are usually in this<br />
category of “mere technical details”
Overview of R&D Activities at ANSTO<br />
Cory J Hamelin<br />
Australian Nuclear Science and Technology Organisation, New Illawarra Road, Lucas Heights NSW 2234 Australia<br />
Presented at the 13 th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
Jeju, Republic of Korea, 7-9 September 2015
74
ANSTO and Nuclear Fuel Cycle R&D<br />
• Fuel/cladding interactions<br />
– Use of atomistic modelling (e.g. DFT)<br />
• Structural materials performance under extreme<br />
conditions<br />
– Irradiation, corrosion, high temperatures and/or deformation<br />
• Separation science<br />
– Synthesis and analysis of titania frameworks for separation of U, Pu<br />
• Wasteform fabrication<br />
– Construction of a Synroc waste treatment plant to reduce volume of ANSTO<br />
nuclear by-products by 99%<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
75
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
76
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
77
Radiation Damage Test Environments at ANSTO<br />
• 1MV VEGA accelerator<br />
• 2MV STAR tandetron accelerator<br />
• 6MV SIRIUS tandem accelerator<br />
• 10MV ANTARES tandem accelerator<br />
– Energies from < 1 MeV to 100 MeV<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
78
79
Specimens for Neutron Irradiation<br />
• Miniature dogbone samples<br />
• Small punch discs<br />
• Compact tension discs<br />
• Quarter-size Charpy samples<br />
• Corrosion samples<br />
1 dpa/yr<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
80
Samples Currently in OPAL (or Planned for Insertion)<br />
<strong>Material</strong> Sample type Irradiation time Source<br />
MA957 TEM discs 460 days IME/ORNL i<br />
CLAM “ “ IME i<br />
TiAl FT “ “ IME/LANL ii<br />
AlMg5 Mini tensile “ IME/OPAL Surveillance iv<br />
Zr-3.5Sn “ 460 days IME/Queens ii<br />
TiAl DP TEM discs 460 days IME/LANL ii<br />
Ti-6Al-4V “ “ IME i<br />
Zr-2.5Nb “ “ IME i<br />
Zr-4 CT 460 days OPAL Surveillance iv<br />
Zr-4 CT 5 years OPAL Surveillance iv<br />
Zr-4 CT 10 years OPAL Surveillance iv<br />
NiCrMoFe Small Punch 460 days IME/SINAP JRC iii<br />
NiCrMoFe “ 920 days IME/SINAP JRC iii<br />
Ti45Al “ 460 days IME i<br />
Ti45Al2Nb “ “ IME i<br />
Ti45Al TEM disc “ IME i<br />
Ti45Al2Nb “ “ IME i<br />
Zr-2.5Nb “ “ IME/OPAL i<br />
NiCrMoFe “ “ IME/SINAP JRC iii<br />
Zr-3.5Sn Mini Tensile 5 years IME/Queens ii<br />
NiCrMoFe “ 460 days IME/SINAP JRC iii<br />
Al6061 “ 5 years OPAL Surveillance iv<br />
i<br />
Internal research<br />
ii<br />
unfunded collaborative research<br />
iii<br />
partially funded research with external partners<br />
iv<br />
OPAL <strong>Material</strong>s Surveillance Program (MSP)<br />
• Zr and Al alloys<br />
– Predominantly for OPAL support<br />
• Titanium Aluminides<br />
– Internal research<br />
• Ni alloys<br />
– Collaborative work (SINAP <strong>MSR</strong>)<br />
• Additional planned materials<br />
– A508 (PM, WM, HIP)<br />
– ODS<br />
– Graphite<br />
– Tungsten<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
81
Active Sample Machining and Testing<br />
• Active samples sent to MEHC, which contains:<br />
– Mechanical testing facilities for active material<br />
– Micromachining facilities to allow samples to exit cells<br />
• MEHC currently in licensing/commissioning stage<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
82
The Role of Ion Irradiation<br />
• Current limitations on neutron fluence<br />
– Irradiating at coolant water temperature (higher temperatures desirable)<br />
• Ion irradiation allows for higher dpa<br />
– Proton and alpha damage of thin samples<br />
– Self irradiation of energetic heavier ions<br />
• Must be accompanied by modelling of the processes<br />
to enable correlation of ion vs. neutron damage<br />
• Useful for preliminary qualification of nuclear structural<br />
materials<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
83
Single Crystal Ni, He+ Ion Irradiation<br />
11.85 µm<br />
~ 19 dpa<br />
Irradiation<br />
direction<br />
Front surface<br />
(Entry surface)<br />
Back surface<br />
(Exit surface)<br />
~ 10 dpa<br />
SRIM (The Stopping and Range of Ions in Matter) estimates for He+ irradiation of Ni<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
84
Micromechanical Testing<br />
Radiation direction<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
85
Trends in Irradiation Strengthening with Dose<br />
• <strong>Material</strong>s performance under ion irradiation provides useful qualitative information<br />
• Full-sample performance does not explicitly consider localised damage<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
86
Layered Irradiation Studies<br />
Ar implanted layer<br />
Ar implanted layer<br />
He implanted<br />
layer<br />
Cu tape<br />
• Increases width of peak damage layer in specimen<br />
– Subjected to hardness testing to determine deformation mechanism(s)<br />
• <strong>Material</strong>s tested include Ti6Al4V, ODS (MA957), Zr-4<br />
and AISI 316<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
87
Variation in Radiation Damage Morphology<br />
Cross-section TEM of irradiated and indented AISI 316 sample (extracted with FIB)<br />
Top surface<br />
Few bubbles<br />
(Ar)<br />
Radiation damage<br />
Ar<br />
He<br />
Bubbles<br />
(He)<br />
Bubbles<br />
(He)<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
88
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
89
Creep Rupture Assessment<br />
• Member of the R5 EDF Energy Code of Practice development panel (“Assessment<br />
Procedure for the High Temperature Response of Structures”)<br />
• Component life assessment using advanced damage accumulation models (SMDE,<br />
SEDE), considering multi-axial effects<br />
• <strong>Material</strong>s studied largely ferritic steels (P22, P91, CMV, etc.), some austenitic steels<br />
(e.g. AISI 316H) and Ni alloys (Ni 201, Inconel 600)<br />
1000<br />
450 C<br />
Stress (MPa)<br />
500<br />
450<br />
400<br />
350<br />
300<br />
250<br />
200<br />
150<br />
ANSTO<br />
NIMS<br />
JAEA<br />
CFAT<br />
CRIEPA<br />
ORNL<br />
NIMS-2<br />
ORNL2<br />
Energy Density MJ/m 3<br />
100<br />
10<br />
500 C<br />
550 C<br />
600 C<br />
650 C<br />
700 C<br />
Fit 450 C<br />
Fit 500 C<br />
Fit 550 C<br />
Fit 600 C<br />
Fit 650 C<br />
100<br />
ODIN<br />
Fit 700 C<br />
50<br />
0<br />
1 10 100 1000 10000 100000<br />
Time to Rupture (Hours)<br />
1<br />
0.000001 0.00001 0.0001 0.001 0.01 0.1 1<br />
Average Strain Rate (1/hr)<br />
Creep rupture data for P91, taken from a variety of sources (left). Energy density predictions using hybrid energy models (right).<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
90
Predicting Creep Rupture<br />
• FEA prediction of in-service materials performance<br />
• User-defined material models for creep strain/damage<br />
Prediction (via FEA) of creep rupture during an accelerated creep test in ex-service AISI 316H stainless steel using<br />
a Strain Energy Ductility Exhaustion (SEDE) creep damage model<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
91
Quantification of Accumulated Creep via EBSD<br />
• Data analysis for performance trends<br />
– Quantifying plasticity (creep vs. fatigue) via EBSD<br />
– Studies on Ni-201 and P22 (underway)<br />
Example of damage characterisation in Ni-201 material: (left) virgin material; (centre) material subjected to<br />
15% creep strain; and (right) damage curve constructed to assess creep life<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
92
Creep-Fatigue Tests<br />
• Laboratory testing predominantly high-Cr ferritic steels (P91, P92) as part of<br />
collaborative study in MATTER FP7 (MATerials Testing and Rules for Generation IV<br />
<strong>Reactor</strong>s), WP4 (Prenormative R&D for Codes and Standards)<br />
Observed Nf<br />
100000<br />
10000<br />
1:1<br />
X2<br />
X2<br />
Energy Modified Exhaustion<br />
Stress Modified Exhaustion<br />
RCC-MR (Time Fraction)<br />
Time Fraction<br />
Ductility (Elongation)<br />
Power (Energy Modified Exhaustion)<br />
Power (Stress Modified Exhaustion)<br />
Power (RCC-MR (Time Fraction))<br />
Power (Time Fraction)<br />
Power (Ductility (Elongation))<br />
1000<br />
100<br />
10 100 1000 10000 100000<br />
Predicted Nf<br />
ANSTO P91 creep-fatigue tests were used with test data from ORNL, CEA, EPRI and IGCAR to assess the accuracy of new and existing<br />
damage models (TF, SMDE and SEDE shown) in predicting material failure. Test data conducted at 450-700 ºC, resulting in rupture times<br />
ranging from 2-50,000 h.<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
93
P91 Japan Sodium-Cooled Fast <strong>Reactor</strong> Tubesheet<br />
• Hot transient sodium temp = 600 C (2hr dwell)<br />
• Cold transient temp = 250 C (1 hr hold)<br />
• Rate Change = 5 C/s<br />
• Cycle length = 3 h and 140s per cycle<br />
• Number of test cycles = 1873<br />
• Crack initiation mode creep-fatigue<br />
• Maximum Crack Length = 3.7 mm<br />
Ando (2014)<br />
Original JAEA analyses performed using RCC-MR<br />
time fraction (TF) models for P91. Strain ranges<br />
derived using: (i) Stress Redistribution Locus, SRL;<br />
(ii) Simple Elastic Follow-Up, SEF; and (iii) direct<br />
inelastic implementation using FEA. ANSTO-EDF<br />
Energy analyses (in red) used inelastic strain range<br />
with ductility exhaustion models.<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
94
Creep-Fatigue <strong>Material</strong>s Database<br />
• Creation of a materials database for creep-fatigue<br />
performance<br />
Full C-F Model<br />
1Cr0.5Mo (P12) 1.25Cr0.5Mo (P11) 2.25Cr1Mo (P22)<br />
0.5Cr0.5Mo0.25V (CMV) 1Cr1Mo0.25V (CMV) 1.25Cr1Mo0.25V (CMV)<br />
P9 X10CrMoVNb (P91) 9Cr0.5Mo1.8WVNbB (P92)<br />
AISI 304 AISI 316 25Cr35NiNbMa (HK40)<br />
X20CrMoV12-1 7-9Cr2WV P23<br />
Hastelloy XR Fe0.75Ni0.5MoCrV Fe2.25Cr1Mo0.25V<br />
Under Development<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
95
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
96
Corrosion Testing<br />
• ANSTO-SINAP JRC (<strong>MSR</strong>)<br />
– FLiNaK salt composition<br />
– Tests conducted at 750ºC for 10, 100<br />
and 200 h<br />
• <strong>Material</strong>s tested<br />
– NiCrMoFe<br />
– Graphite<br />
– AISI 316<br />
Controlled atmosphere furnace (above) with temperature<br />
control directly linked to salt temperature; exposed NiCrMoFe<br />
is examined via EDS (left) to determine surface degradation.<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
97
<strong>Salt</strong> Infiltration into Graphite<br />
<strong>Salt</strong> infiltration into various grades of graphite (right, top) at different pressures<br />
(above): (a) 1.0 atm; (b) 1.5 atm; (c) 3.0 atm; and (d) 5.0 atm. Location of salt<br />
quantified via EDS (right) and neutron tomography (DINGO).<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
98
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
99
Combined Effects of Corrosion and Ion Irradiation<br />
• NiCrMoFe alloy, FLiNaK salt, 10 17 ions/cm 2 He+<br />
As-Received<br />
Irradiated, No Corrosion<br />
Corrosion, No Radiation<br />
Irradiated + Corrosion<br />
Pt-Ni interface measured using STEM-EDS under four conditions representing various combinations of corrosion and radiation damage. The<br />
relative increase in interface layer before and after corrosion represents the corrosion layer. This layer is 20 nm for the as-received material,<br />
and 700 nm for the irradiated material.<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
100
Combined Effects of Corrosion and Ion Irradiation<br />
• Graphite, FLiNaK salt, 10 17 ions/cm 2 He+<br />
As-Received<br />
Irradiated, No Corrosion<br />
Corrosion, No Radiation<br />
Irradiated + Corrosion<br />
Graphite test coupons were irradiated using 30 keV He+ ions; one section of the<br />
sample was masked to prevent radiation damage (right). The samples were<br />
then exposed to molten FLiNaK salt (150 h @ 750 ºC). Clear variations in the<br />
corroded structures are visible (above).<br />
Damaged<br />
Masked<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
101
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
102
<strong>Material</strong>s Testing at High Temperatures<br />
• NiCrMoFe creep rupture test (190 MPa @ 700 ºC)<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
103
ANSTO and Generation IV Structural <strong>Material</strong>s R&D<br />
• Irradiation<br />
– Neutron, ion damage studies<br />
• High temperature<br />
– Creep testing<br />
• Corrosion<br />
– Testing in molten salt environments<br />
• Combined environments<br />
– Irradiation + corrosion (<strong>MSR</strong>)<br />
– Corrosion + high temperature<br />
– Irradiation under high temperature<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
104
High Temperature Irradiation (Planned)<br />
• Motivation<br />
– Radiation damage is controlled by a thermally<br />
activated processes, so some temperature<br />
control is desirable<br />
• Planned Work<br />
– Neutronics/gamma heating calculations<br />
– Thermal hydraulics calculations (safety case)<br />
– Can design and T&C specifications<br />
Muroga (2001)<br />
OPAL contains empty space (“hot<br />
source”) in the RPV. By developing a<br />
suitable holder (such as the ORNL<br />
HFIR sample heating holder, left),<br />
samples may be irradiated in OPAL at<br />
higher temperatures, thereby enabling<br />
elevated-temperature damage mechanisms<br />
to be characterised. Kiritani (1988)<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
105
Additional Considerations: Welding<br />
• Understanding of microstructure and stress state<br />
around single- and multi-pass welded joints<br />
• Heavily involved in international round-robin<br />
programmes designed to identify best practise for joint<br />
characterisation and process simulation<br />
– NeT (AISI 316, Inconel 600, A508)<br />
– USNRC (DMW)<br />
• ANSTO carries out materials testing for materials data<br />
set required for simulation, as well as characterisation<br />
and performance evaluation of welded joints<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
106
<strong>Material</strong> Test Data (High-Temperature LCF)<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
107
Process Simulation: DMW<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
108
Process Simulation: EB Weld (A508)<br />
Temperature<br />
Distribution<br />
Stress<br />
Distribution<br />
Martensite<br />
Formation<br />
Bainite<br />
Formation<br />
Courtesy A. Vasileiou, University of Manchester<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
109
ANSTO-University of Manchester RCA<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
110
Weld Characterisation (NiCrMoFe)<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
111
Conclusions<br />
• Variety of structural materials R&D has been, is and will<br />
be conducted at ANSTO<br />
– Much of that work is related to Generation IV systems, particularly for VHTR and<br />
<strong>MSR</strong> environments<br />
• Radiation, high-temperature, and corrosion<br />
environments considered (alone or in concert)<br />
– Characterisation (both ex situ and in situ), testing and analysis performed<br />
• Numerous materials under investigation<br />
– Apart from materials critical to ANSTO infrastructure, feedback through bodies<br />
such as the VHTR PMB essential for future research planning<br />
Overview of ANSTO R&D Activities<br />
13th Meeting of the <strong>Material</strong>s Project Management Board for the GIF VHTR System<br />
112
ANSTO as a National Laboratory<br />
• Undertake and facilitate research in the national<br />
interest<br />
• Produce and provide state-of-the-art<br />
radiopharmaceuticals for Australia and the world<br />
• Provide trusted advice to Government in all<br />
aspects of the Nuclear Fuel Cycle<br />
• Operating ANSTO’s nuclear facilities including the<br />
OPAL nuclear research reactor in a safe and<br />
efficient manner
ANSTO Nuclear Medicine Project<br />
• 80% of all nuclear medicine procedures use<br />
Mo-99/Tc-99m<br />
• Diagnosing heart disease, cancer,<br />
neurological disorders and more.<br />
SINAP NiMo-SiC Alloy<br />
• 40 million patients per year<br />
• Global market of US$550 million per annum<br />
• Potential critical worldwide Mo-99 shortage<br />
• A new Australian Mo-99 production facility<br />
• Mo-99 production capacity to allow for<br />
increased exports<br />
• First full scale operational Synroc facility in<br />
the world
GH3535 Creep Conclusions<br />
• GH3535 alloy creep tested at 650, 700, and 750 o C at 85-320 MPa.<br />
• Alloy displayed no primary creep and good creep ductility (above 30%.)<br />
• Using minimum creep rates the calculated stress exponent is n = 5-6 so<br />
dislocation climb is the main creep mechanism<br />
• Formation of dislocation networks and sub-grains confirmed by TEM and<br />
EBSD analysis.<br />
• The Dorn Shepard and Larson Miller master curves were derived to 1%<br />
creep strain and creep rupture respectively.<br />
• Using ASME BPVC guidelines the maximum allowable design stress at<br />
700 o C is 35 MPa.<br />
• There is substantial second phase particle precipitation during creep.