Update on ORNL Diagnostic and Tungsten Armor Efforts Keith Leonard, Glenn Romanoski, Lance Snead Oak Ridge National Laboratory Nalin Parikh UNC, Chapel.

Slides:



Advertisements
Similar presentations
18 th International Conference on Plasma Surface Interaction in Controlled Fusion Toledo, Spain, May 26 – 30, Deuterium trapping in tungsten damaged.
Advertisements

© Olga Ogorodnikova, 2008, Salamanka, Spain Current status of assessment of Tritium inventory in all-W device O.V. Ogorodnikova and E. d’Agata.
HYDROGEN INTERACTION WITH NICKEL CONTAINING RADIOGENIC HELIUM.
M. S. Tillack, J. E. Pulsifer, K. L. Sequoia Grazing-Incidence Metal Mirrors for Laser-IFE Third IAEA Technical Meeting on “Physics and Technology of Inertial.
September 24-25, 2003 HAPL meeting, UW, Madison 1 Armor Configuration & Thermal Analysis 1.Parametric analysis in support of system studies 2.Preliminary.
1 EFFECTS OF CARBON REDEPOSITION ON TUNGSTEN UNDER HIGH-FLUX, LOW ENERGY Ar ION IRRADITAION AT ELEVATED TEMPERATURE Lithuanian Energy Institute, Lithuania.
Deal-Grove Model Predictions Once B and B/A are determined, we can predict the thickness of the oxide versus time Once B and B/A are determined, we can.
Investigations on Applicability of Dielectric Mirrors for ITER Orlovskiy, Konstantin Vukolov Ilya Orlovskiy, Konstantin Vukolov 10 th ITPA Meeting Group,
Structural response of SiC and PyC on swift heavy ion irradiation
Government Labs 1.NRL 2.LLNL 3.SNL 4.LANL 5.ORNL 6.PPPL Universities 1.UCSD 2.Wisconsin 3.Georgia Tech 4.UCLA 5.U Rochester 6.PPPL 7.UC Santa Barbara 8.UNC.
Dynamic hydrogen isotope behavior and its helium irradiation effect in SiC Yasuhisa Oya and Satoru Tanaka The University of Tokyo.
Study of sputtering on thin films due to ionic implantations F. C. Ceoni, M. A. Rizzutto, M. H. Tabacniks, N. Added, M. A. P. Carmignotto, C.C.P. Nunes,
Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)
November 8-9, “Engineering Analysis” of He Retention & Release Experiments to Determine Desirable Engineered W Armor Microstructure A. René Raffray.
Background on GIMM studies in HAPL Challenges for a final optic optical requirements environmental threats system integration Design choices Logic pursued.
UV laser-induced damage to grazing- incidence metal mirrors M. S. Tillack, J. Pulsifer, K. Sequoia 4th US-Japan Workshop on Laser-Driven Inertial Fusion.
Plasma Processes, Inc. Scott O’Dell12/3/20021 Introduction Plasma Processes, Inc. is a small business that specializes in the development and fabrication.
Performance of Dielectric Mirrors for Inertial Fusion Application Lance Snead, Keith Leonard, and Jay Jellison Oak Ridge National Laboratory Mohamed Sawan.
Chapter 8 Ion Implantation Instructor: Prof. Masoud Agah
ECE/ChE 4752: Microelectronics Processing Laboratory
1Managed by UT-Battelle for the Department of Energy HAPL Meeting Oct st, 2007 Review of ORNL Collaborative Materials Development Work in Support.
OVERVIEW Material Irradiation Damage Studies at BNL BLIP N. Simos and H. Kirk, BNL K. McDonald, Princeton U N. Mokhov, FNAL (Oct. 20, 2009) (BLIP = Brookhaven.
R. Parker, (R. Scelle), (S. Gilliam), and N. R. Parikh University of North Carolina at Chapel Hill, Chapel Hill, NC R. G. Downing National.
Computational Nano & Micro Mechanics Laboratory UCLA Measurement of Tungsten Armor - Ferritic Steel Interfacial Bond Strength Using a Nanosecond Laser.
HAPL WORKSHOP Chamber Gas Density Requirements for Ion Stopping Presented by D. A. Haynes, Jr. for the staff of the Fusion Technology Institute.
Plasma Arc Lamp Operation
Review of Results First Wall Helium Management & Refractory Armored Materials L L Snead, T. Hinoki, J. Hunn, C. Blue, N. Hashimoto (ORNL) R. Raffray (UCLA)
Integrated Materials Plan Progress: Helium Blistering and Refractory Armored Materials Lance L Snead High Average Power Lasers Workshop December 6, 2002.
Measurement and modeling of hydrogenic retention in molybdenum with the DIONISOS experiment G.M. Wright University of Wisconsin-Madison, FOM – Institute.
1 Scoping the Potential of Mobile Tiles for and IFE Power Plant Lance Snead, Hsin Wang, Jim Kiggans Oak Ridge National Laboratory Igor Sviatoslavsky, Mohamed.
O AK R IDGE N ATIONAL L ABORATORY U. S. D EPARTMENT OF E NERGY 1 Tungsten Armored Ferritic Steel Glenn Romanoski & Lance Snead June 2004.
Tritium Retention in Graphite and Carbon Composites Sandia National Laboratories Rion Causey Sandia National Laboratories Livermore, CA
Plan to Develop A First Wall Concept for Laser IFE.
NEEP 541 – Radiation Damage in Steels Fall 2002 Jake Blanchard.
NANO 225 Micro/NanoFabrication Electron Microscopes 1.
Low temperature dissipation in coating materials S. Reid 1, I. Martin 1, H. Armandula 3, R. Bassiri 1, E. Chalkley 1 C. Comtet 4, M.M. Fejer 5, A. Gretarsson.
Introduction. Like a house consisting of rooms separated by walls, a crystalline material consists of grains separated by grain boundaries. Within a grain,
O AK R IDGE N ATIONAL L ABORATORY U. S. D EPARTMENT OF E NERGY 1 Update on Helium Retention Behavior in Tungsten D. Forsythe, 1 S. Gidcumb, 1 S. Gilliam,
Center for Materials for Information Technology an NSF Materials Science and Engineering Center Substrate Preparation Techniques Lecture 7 G.J. Mankey.
Control of Carbon Nanotube Nucleation Rate with a Hydrogen Beam Plasma Paolo Santos 1, Dorothée Alsentzer 3, Thomas B. Clegg 2,3, Sergio Lemaitre 2,3,
The effect of displacement damage on deuterium retention in plasma-exposed tungsten W.R.Wampler, Sandia National Laboratories, Albuquerque, NM R. Doerner.
The tungsten/F82H sample was impinged at 6 different locations with 6 different laser fluence energies to determine the critical energy that would result.
Overview of HAPL First Wall Materials Issues HAPL Materials and Design Team HAPL Average Power Laser Program Workshop Princeton Plasma Physics Laboratory.
Electro-Ceramics Lab. Electrical Properties of SrBi 2 Ta 2 O 9 Thin Films Prepared by r.f. magnetron sputtering Electro-ceramics laboratory Department.
Plasma Processes, Inc. February 5-6, Engineered Tungsten for IFE Dry Chamber Walls HAPL Program Meeting Georgia Institute of Technology Scott O’Dell,
Surface Effects and Retention of Steady State 3 He + Implantation in Single and Polycrystalline Tungsten S.J. Zenobia, G.L. Kulcinski, E. Alderson, G.
10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.
Helium Retention Studies in Tungsten
Effect of Re Alloying in W on Surface Morphology Changes After He + Bombardment at High Temperatures R.F. Radel, G.L. Kulcinski, J. F. Santarius, G. A.
Ion Beam Analysis of the Composition and Structure of Thin Films
Ion Beam Materials Analysis and Modifications Group University of North Carolina at Chapel Hill Helium Threat Spectrum Implantation in Tungsten S. Gilliam.
9 th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials Salamanca, Spain, June 2 - 3, Simulation experiments on neutron damage.
Effect of Mirror Defect and Damage On Beam Quality T.K. Mau and Mark Tillack University of California, San Diego ARIES Project Meeting March 8-9, 2001.
IFE Ion Threat Spectra Effects Upon Chamber Wall Materials G E. Lucas, N. Walker UC Santa Barbara.
O AK R IDGE N ATIONAL L ABORATORY U. S. D EPARTMENT OF E NERGY 1 Chamber Materials Progress Round Robin Materials Refractory Armored Ferritic Helium Management.
Low temperature dissipation in coating materials S. Reid 1, I. Martin 1, E. Chalkley 1, H. Armandula 3, R. Bassiri 1, C. Comtet 4, M.M. Fejer 5, A. Gretarsson.
ALD Oxides Ju Hyung Nam, Woo Shik Jung, Ze Yuan, Jason Lin 1.
Investigation of the Performance of Different Types of Zirconium Microstructures under Extreme Irradiation Conditions E.M. Acosta, O. El-Atwani Center.
1. Feb 2001:NRL 2. May 2001:NRL 3. Nov 2001:LLNL 4.Apr 2002:GA 5. Dec 2002:NRL 6. Apr 2003:Sandia 7. Sep 2003:Wisconsin 8. Feb 2004:Georgia Tech 9. Jun.
M. S. Tillack, J. E. Pulsifer, K. Sequoia Final Optic Research – Progress and Plans HAPL Project Meeting, Georgia Tech 5–6 February 2004.
Effects of Pulsed He + Irradiation on Tungsten Surfaces R.F. Radel, G.L. Kulcinski, S.J. Zenobia HAPL Meeting-ORNL March 22 nd, 2006 Fusion Technology.
S.I. Golubov, S.J. Zinkle and R.E. Stoller
Micro-engineered Armor:
Characterization of He implanted Eurofer97
A comparison of optical trains based on a GIMM
Update on Helium Management and Tungsten Bonded Ferritic
Modeling Carbon Diffusion in W-Armor
Tungsten Armor Engineering:
Helium Behavior and Surface Roughening of Solid Tungsten
Presentation transcript:

Update on ORNL Diagnostic and Tungsten Armor Efforts Keith Leonard, Glenn Romanoski, Lance Snead Oak Ridge National Laboratory Nalin Parikh UNC, Chapel Hill Shahram Sharafat Out West Presented at the HAPL Meeting PPPL, Princeton, NJ December 12-13, 2006

Model Carbon diffusion with Temperature evolution (t=0 use spatial Carbon implantation profile and “end of shot” temperature profile) Carbon Buildup In W-Armor Carbon Implantation Profile Carbon Concentration Within ~ 10 days of operation C-concentration = W-concentration

Objectives for performing carbon ion implantation in tungsten C ions (~ 0.5 MeV) will be implanted in W samples heated to IFE surface-relevant temperatures (~2000C). Tungsten samples will include two plasma sprayed tungsten materials and other candidates used for He implantation. Models for carbon implantation will be validated and refined. Response of W to high-dose carbon implantation and tungsten carbide formation will be assessed. Mobility of carbon through porous, plasma sprayed microstructures will be quantified. Combined effect of C and He implantation will be assessed.

Development of VPS W/LAF 10.0kX20.0keV 1.0 µm O C F82H Steel Interface Tungsten We are considering the VPS W/LAF sufficiently mature. Have withstood 10,000. Continuing long term aging of interface (currently > 10,000hr) Next series of thermal fatigue tests planned for long-term aged and carbon implanted material.

The flux of carbon ions into the W armor surface ensures the formation of tungsten carbide The formation of W 2 C and WC is likely to cause near surface dilatation and spallation damage. A tungsten carbide reaction zone will likely affect He damage. Carbon ions near the surface are a potential source of Carbon to the W/FS interface.

C dose: 1.4 E19 c/cm 100K eV Polycrystalline tungsten was implanted with carbon ions by UNC at RT followed by annealing at 2000ºC for 5 min. XRD analysis confirmed the formation of W 2 C Under 1 micron

Carbon Implanted Tungsten Step 1: Carbon implantation Polycrystalline W 1.4x10 19 cm -2 Room temperature Step 2: Thermal anneal Electrical resistance heating 2000ºC 5 minutes Cross-section from sample milled out by focused-ion beam (FIB) for TEM examination. Implanted surface Grain #1 Grain #2 Grain #3 Grain #4 Grain #5 Depth into sample Milling artifacts from FIB Grain boundaries

Carbon Implanted Tungsten Implanted surface Grain #1 Grain #2 Grain #3 Grain #4 Grain #5 Milling artifacts from FIB Grain boundaries Depth into sample Particles observed along grain boundaries. Discontinuous along boundaries. Typically 100 to 200 nm in size. Observed to a depth of 7.6  m from surface.

Carbon Implanted Tungsten Implanted surface Grain #1 Grain #2 Grain #3 Grain #4 Grain #5 Milling artifacts from FIB Grain boundaries Depth into sample Particles observed in grain (#1) near implantation surface. Needle-like, consisting of segments. Up to 2  m long, 25 nm thick. Observed to a depth of 2.6  m from surface.

Carbon Implanted Tungsten Implanted surface Grain #1 Grain #2 Grain #3 Grain #4 Grain #5 Milling artifacts from FIB Grain boundaries Depth into sample Particles observed along grain boundaries. Discontinuous along boundaries. Typically 100 to 200 nm in size. Observed to a depth of 7.6  m from surface.

Helium Implantation Studies of Simulated Irradiation Damage to Aluminum Mirror Performance Issue: He implantation of aluminum mirrors is used as a first approach at simulating the changes in optical properties and performance of mirrors in the IFE under irradiation. The degree of surface roughening and the resulting degradation in optical performance of metal mirrors for the IFE as a result of charged particle implantation and neutrons is an important issue that has not been well addressed. Material: 1 inch diameter electrodeposited aluminum, 250 micron thick, on 6061-T6 aluminum substrate – manufactured by AlumiPlate Inc. Diamond turned mirror surface, between 40 to 46 Å surface roughness- turned by II-VI Infrared. He Implantation: Performed by Nalin Parikh and Shon Gilliam, UNC-Chapel Hill. Use of beam mask allowing for multiple implantation tests per sample. 110 keV, 4 He implantation. 1x10 19, 1x10 20 and 1x10 21 He/cm 2 0, 30 and 60º angle of incidence. Room temperature implantation. Implantations produce a range of damage from 0.01 to 2 dpa at 100 nm below the surface for the various conditions based on SRIM code simulation. Current Status of Work: Samples received at ORNL for optical measurements. Some discoloration on the surface for the He/cm 2 locations. Samples currently –Optical ellipsometry techniques for changes in quality. –Atomic Force Microscopy for changes in surface roughness. –SEM examination of surface roughness. 1x10 19 He/m 2 0º tilt 1x10 20 He/m 2 0º tilt 1x10 21 He/m 2 0º tilt 1x10 21 He/m 2 30º tilt 1x10 20 He/m 2 30º tilt 1x10 19 He/m 2 30º tilt 1x10 21 He/m 2 1x10 20 He/m 2 1x10 19 He/m 2 All at 60º tilt Sample 1 Sample 2

Update: Irradiation Damage on Dielectric Mirror Performance Dielectric Mirrors Films deposited by E-beam with ion-assist on sapphire substrates. Quarter wavelength bi-layers of HfO 2 / SiO 2, HfO 2 / Al 2 O 3 and Al 2 O 3 / SiO 2. Quarter wavelength monolayers of HfO 2 (26.9 nm thick), Al 2 O 3 (36.5 nm thick) and SiO 2 (40.5 nm thick) on sapphire. Tasks Phase 1, FY-06: He implantation –Collaboration with Nalin Parikh (UNC) –Tests conducted on monolayer films only to evaluate film/substrate interactions. Phase 2, FY-07: Neutron irradiation –Collaboration with T. LaHecka (Penn. State) and M. McGeoch (Plex Corp.) –Irradiation at High Flux Isotope Reactor and post irradiation evaluation at ORNL.

Changes to Monolayer Thin-Films Following Helium Ion Implantation Issue: Multilayered dielectric mirrors could significantly improve transmission of reflected electromagnetic energy, but little is known about their longevity and performance in IFE relevant environments. Preliminary work on performance of dielectric mirrors under neutron irradiation has been inconclusive. This is due in part to the behavior of the constituent film layers under irradiation and the film/substrate interface interactions not being understood. Material: E-beam / ion-assist deposited films of quarter wavelength thick: Al 2 O 3 (36.5 nm thick) on sapphire SiO 2 (40.5 nm thick) on sapphire HfO 2 (26.9 nm thick) on sapphire Un-coated sapphire for control He Implantation: Phase 1 of study (Phase 2,HFIR Neutron Irradiation). Performed by Nalin Parikh and Shon Gilliam, UNC Use of beam mask allows multiple implantation tests. 110 keV, 4 He implantation, 0º tilt, room temperature , 10 19, and He/m 2. Implantation conditions produce to 1 dpa of damage at the film/substrate interface – SRIM calculations. Current Status of Work: General inspection of films by SEM showed no signs of delamination or blistering. Atomic force microscopy carried out to determine changes in surface roughness and step height differences between implanted and non-implanted regions. Optical examination by ellipsometry techniques for changes in quality pending. He implantation mask

Changes to Monolayer Thin-Films Following Helium Ion Implantation AFM data. SiO 2 monolayer on sapphire. 1x10 18 and 1x10 19 He/m 2 dose. No significant difference observed on film surface. Ellipsometry and high-resulution SEM underway

Nalin et al. has performed Carbon implantation on three polycrystalline tungsten samples at ambient temperatures followed by annealing at 2000C for 5 minutes. The samples include the following C+ Doses: I believe all are 100KeV implantation voltage. Nalin can confirm. GM2 1.4E19 cm-2 GM3 3.6E17 cm-2 GM4 5.4E17 cm-2 X-ray diffraction confirms W2C formation in all samples. The diffraction pattern attached for GM2 shows some shift from the perfect W2C lattice due to non-stochiometry according to Burl Cavin (see phase diagram). Keith has confirmed the presence of W2C in the GM2 sample.

Effects of Carbon Implantation (ORNL/UNC/UCLA) Issue: About 6.8x10 19 per shot Carbon atoms are released from the 365 MJ Target (10 m Chamber): –~1.7 appm per shot Carbon in Tungsten  in about 1x10 6 shots C/ W ~ 1.7 ( Hz) –~0.7 appm per shot Carbon in SiC  in about 1x10 6 shots C/ W ~ 0.7 ( Hz) Goals: (1) Investigate the Behavior of Carbon Implantation : –Free or bound Carbon (WC and W 2 C) ? –Release of Carbon from surface or Diffusion of Carbon toward W/Steel Interface ? (2) Investigate Helium Release from Carbon Implanted Region : –Helium release Experiments: Follow Sample Handling Procedure (1) UNC Carbon Implantation (Single-X W) Steady State followed by 1 Annealing Cycle: Implantation at T = 850°C, <0.5 MeV Total C-Fluence = 1.6x10 22 C/m 2 (eq. to ~3x10 5 shots or ~ ½ day at 10 Hz)  C/ W ~ 0.5 Anneal at 2000°C for ~430 sec (total time above 1000 C for ~3x10 5 shots) Determine depth profile and density of Carbon & Perform Hardness measurements (2) UNC Helium Implantation (use Carbon exposed SX-W). Step wise He followed by 2000 C annealing: Implant 1x He/m 2 at 850°C, flash anneal at 2000°C in 1000 or 100 steps Determine Helium release and depth profile. Modeling: –Modify Carbon Diffusion model (UCLA) to include WC and W2C formation –Add Carbon Implantation/Carbide Formation to the HEROS code He model (UCLA): Account for large damage rates caused during C-implantation and short time at T.