Characterization of He implanted Eurofer97

Slides:



Advertisements
Similar presentations
PWI Modelling Meeting – EFDA C. J. OrtizCulham, Sept. 7 th - 8 th, /8 Defect formation and evolution in W under irradiation Christophe J. Ortiz Laboratorio.
Advertisements

D retention in O-covered and pure beryllium
18 th International Conference on Plasma Surface Interaction in Controlled Fusion Toledo, Spain, May 26 – 30, Deuterium trapping in tungsten damaged.
Investigation of Proton Irradiation-Induced Creep of Ultrafine Grain Graphite Anne A. Campbell & Gary S. Was University of Michigan Research Supported.
M.G. Ganchenkova 1, V.A. Borodin 2, R. Nieminen 1 1 COMP/Laboratory of Physics, Helsinki University of Technology, Espoo, Finland 2 RRC Kurchatov Institute,
Experimental studies of low energy proton irradiation of thin vacuum deposited Aluminum layers T. Renger, M. Sznajder, U.R.M.E. Geppert Chart.
NEEP 541 – Creep Fall 2002 Jake Blanchard.
HYDROGEN INTERACTION WITH NICKEL CONTAINING RADIOGENIC HELIUM.
Extended Defects in c-Si (Claverie etc, MSSP 3, 269 (2000) CEC Inha University Chi-Ok Hwang.
L.B. Begrambekov Plasma Physics Department, Moscow Engineering and Physics Institute, Moscow, Russia Peculiarities, Sources and Driving Forces of.
NEEP 541 – Defects Fall 2003 Jake Blanchard. Outline Irradiation Induced Defects Definitions Particles Cascades Depleted zones Thermal Spikes.
Dynamic hydrogen isotope behavior and its helium irradiation effect in SiC Yasuhisa Oya and Satoru Tanaka The University of Tokyo.
AUGER ELECTRON SPECROSCOPY. Auger Electron Spectroscopy (AES) was developed in the late 1960's deriving its name from the effect first observed by Pierre.
November 8-9, “Engineering Analysis” of He Retention & Release Experiments to Determine Desirable Engineered W Armor Microstructure A. René Raffray.
Deuterium retention mechanisms in beryllium M. Reinelt, Ch. Linsmeier Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany.
A.V. Kozlov, I.A. Portnykh, V.L. Panchenko FSUE «INM», , Box 29, Zarechny, Sverdlovsk region, Russia Corresponding author. fax: ;
Ryan Weed Centre for Antimatter- Matter Studies VACANCY CLUSTERS IN SELF-ION IMPLANTED GERMANIUM STUDIED WITH PALS.
Ion Implantation Topics: Deposition methods Implant
1Ruđer Bošković Institute, Zagreb, Croatia
J.Vaitkus et al., WOEDAN Workshop, Vilnius, The steady and transient photoconductivity, and related phenomena in the neutron irradiated Si.
Measurement and modeling of hydrogenic retention in molybdenum with the DIONISOS experiment G.M. Wright University of Wisconsin-Madison, FOM – Institute.
International Workshop on “Influence of atomic displacement rate, neutron spectrum and irradiation temperature on radiation-induced ageing of power reactor.
The contribution from The contribution from photoluminescence (PL) Gordon Davies, King’s College London.
Simulating fusion neutron damage using protons in ODS steels Jack Haley.
Post Anneal Solid State Regrowth
Positron and Positronium Chemistry PPC10, September, Smolenice Castle, Slovakia Thermal annealing influence on ions implanted Fe-Cr model alloys.
Kinetic Monte Carlo simulation of irradiation effects in bcc Fe-Cu alloys L. Malerba 1, C. Domain 2, C. S. Becquart 3 and D. Kulikov 1,4,5 COSIRES-7, Helsinki,
Olga Ogorodnikova, 2008, Salamanka, Spain Comments to modelling of hydrogen retention and permeation in tungsten O.V. Ogorodnikova Max-Planck-Institut.
NEEP 541 – Radiation Damage in Steels Fall 2002 Jake Blanchard.
Updates of Iowa State University S. Dumpala, S. Broderick and K. Rajan Oct-2, 2013.
Determination of the 3  fraction in positron annihilation Bożena Jasińska Institute of Physics, Maria Curie Sklodowska University Lublin, Poland.
1 Investigation into properties of neutron and electron irradiated CCD By Nick Sinev University of Oregon Jim Brau, Jan Strube, Olya Igonkina, Nick Sinev.
Russian Research Center” Kurchatov Institute” Theoretical Modeling of Track Formation in Materials under Heavy Ion Irradiation Alexander Ryazanov “Basic.
“Materials for Fission & Fusion Power” Steve Roberts Sergei Dudarev CCFE George Smith Gordon Tatlock Liverpool Angus Wilkinson Patrick Grant Andrew Jones.
The use of both neutron and ion irradiation to show the microstructural origins of strong flux-sensitivity of void swelling in model Fe-Cr-Ni alloys T.
Gamma-induced positron lifetime and age-momentum
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,
NEEP 541 – Graphite Damage Fall 2002 Jake Blanchard.
The effect of displacement damage on deuterium retention in plasma-exposed tungsten W.R.Wampler, Sandia National Laboratories, Albuquerque, NM R. Doerner.
INTERSTITIAL DEFECT REACTIONS IN P-TYPE SILICON IRRADIATED AT DIFFERENT TEMPERATURES L.F. Makarenko*, S.B. Lastovski**, L.I. Murin**, M. Moll*** * Belarusian.
NEEP 541 Displacements in Silicon Fall 2002 Jake Blanchard.
1 Russian Research Center” Kurchatov Institute” Alexander Ryazanov Charge State Effects of Radiation Damage on Microstructure Evolution in Dielectric Materials.
10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.
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
Highlights Highlights of HEROS : First RT model to include spatial dependency of microstructure Ability to model Free-Surfaces implantation, and temperature.
9 th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials Salamanca, Spain, June 2 - 3, Simulation experiments on neutron damage.
HAPL Modeling  Ion and Heat Transport Qiyang Hu, Nasr Ghoniem, Shahram Sharafat, Mike Anderson Mechanical & Aerospace Engineering University of California,
Lecture 7 Lattice Defects, Vacancies PHYS 430/603 material Laszlo Takacs UMBC Department of Physics.
NEEP 541 – Swelling Fall 2002 Jake Blanchard. Outline Swelling.
1 SPIRE Project coordinated by CEA – Contractors : CEA, CIEMAT, CNRS, NRG, ENEA, PSI, KTH, SCK/CEN, FZK « IRRADIATION EFFECTS IN MARTENSITIC STEELS UNDER.
Antihydrogen Workshop, June , CERN S.N.Gninenko Production of cold positronium S.N. Gninenko INR, Moscow.
Investigation of the Performance of Different Types of Zirconium Microstructures under Extreme Irradiation Conditions E.M. Acosta, O. El-Atwani Center.
1 WORKSHOP AND USERS February 2007 Lattice site location of implanted Fe in SrTiO 3 and lattice damage recovery studies A. C. Marques 1,4 *, U. Wahl 1,2,
Microstructural development of HOPG under ion-irradiation ○ Makoto Nonaka 1, Sosuke Kondo 2 and Tatsuya Hinoki 2 1 Graduate school of Energy Science, Kyoto.
Brian D. Wirth*, with valuable conversations and input from HAPL MWG
S.I. Golubov, S.J. Zinkle and R.E. Stoller
Alloy Design For A Fusion Power Plant
Heating and radiological
First Investigation of Lithium Drifted Si Detectors
Information on Be properties
Reminder of few basic facts about displacements per atom (dpa)
Results from the first diode irradiation and status of bonding tests
V2O and V3O DEFECTS IN SILICON: FTIR STUDIES
Australian Nuclear Science and Technology Organisation, Australia
Radiation damage in Trombay nuclear waste glasses
4th n-FAME Workshop – Edinburgh, Scotland (UK) – 4-5 June, 2013
Vacancy defects induced by proton irradiation
Shukui Zhang, Matt Poelker, Marcy Stutzman
Reduced Activation Ferritic Martensitic (RAFM) steels for fusion and fission application Unraveling irradiation-induced embrittlement in steels for nuclear.
Presentation transcript:

Characterization of He implanted Eurofer97 Inês Carvalho, Henk Schut, Alexander Fedorov, Natalia Luzginova, Pierre Desgardin, Jilt Sietsma Edinburgh, 4-5 June 2013

Outline Project overview Techniques Experimental details Results Positron annihilation Thermal desorption spectroscopy Experimental details Results Helium implantations - 500 keV and 2 MeV Helium release mechanisms Example: 500 keV, 1016 He/cm2 Overall picture Final remarks & Future Work

Project Overview Eurofer97 (Fe - 9Cr - 1W - 0.2V - 0.1Ta - 0.1C wt.%) Correlation of microstructure and mechanical properties Understanding structural defects that affect the mechanical properties Evolution of defect structures formed due to clustering and coalescence of POINT DEFECTS Helium-vacancy clusters Helium-filled bubbles Interstitial loops Thermal desorption spectroscopy (TDS) defect populations thermal stabilities of defects Positron annihilation thermal evolution of free-volume related defects Electron Microscopy microstructure of ion implanted and (neutron) irradiated samples

Project Overview Use of thermal desorption spectroscopy (TDS) and electron microscopy on Eurofer97 neutron irradiated material First approach: reproduction of neutron irradiation conditions He implantation with 500 keV and 2 MeV energies Study of defect structures by positron annihilation and Thermal Desorption Spectroscopy (TDS) After: comparison of results – He implanted vs. neutron irradiated samples Reference Material Study of pre-existing defects Ion Implantation (He) Simulation of neutron irradiation defects Neutron Irradiation Real irradiation conditions now

Techniques

Techniques – VEP Positron annihilation 𝑬=𝟓𝟏𝟏 𝒌𝒆𝑽± 𝒄 𝒑 ∕∕ 𝟐 Variable energy positron beam (VEP) 22Na source Energy up to 25 keV (~ 1µm depth for Fe) Thermalization followed by trapping and annihilation Emission of 2𝛾 of 511 keV Lifetime of ~ 200 ps 𝑝 𝑣𝑎𝑙𝑒𝑛𝑐𝑒 𝑒𝑙𝑒𝑐𝑡𝑟𝑜𝑛𝑠 ≪ 𝑝 𝑐𝑜𝑟𝑒 𝑒𝑙𝑒𝑐𝑡𝑟𝑜𝑛𝑠 W parameter  core electrons S parameter  free electrons  vacancies, dislocations, free volumes 𝑬=𝟓𝟏𝟏 𝒌𝒆𝑽± 𝒄 𝒑 ∕∕ 𝟐

Techniques – VEP Positron annihilation 𝑬=𝟓𝟏𝟏 𝒌𝒆𝑽± 𝒄 𝒑 ∕∕ 𝟐 Variable energy positron beam (VEP) 22Na source Energy up to 25 keV (~ 1µm depth for Fe) Thermalization followed by trapping and annihilation Emission of 2𝛾 of 511 keV Lifetime of ~ 200 ps 𝑝 𝑣𝑎𝑙𝑒𝑛𝑐𝑒 𝑒𝑙𝑒𝑐𝑡𝑟𝑜𝑛𝑠 ≪ 𝑝 𝑐𝑜𝑟𝑒 𝑒𝑙𝑒𝑐𝑡𝑟𝑜𝑛𝑠 W parameter  core electrons S parameter  free electrons  vacancies, dislocations, free volumes 𝑬=𝟓𝟏𝟏 𝒌𝒆𝑽± 𝒄 𝒑 ∕∕ 𝟐

Techniques - TDS Thermal desorption spectroscopy Heating rate of 0,33 K/sec Ramp anneal from 300 K up to 1500 K Ultra high vaccum Temperature of released helium related to the type of trap and thermal stability (He-defect binding energy) Amount of He released associated with defect concentration

Experimental details

Experimental TDS PA Energy 500 keV 2 MeV Doses (He/cm2) 1 x 1014-1017 Eurofer97 - Fe-9Cr-1W-0.2V-0.1Ta-0.1C (wt.%) Tempered martensitic structure Ion beam Helium implantation (RT) Sample size: 1.2 x 1.2 x 0.05 cm2 Measurements Positron annihilation DB TDS + in situ DB annealing Energy 500 keV 2 MeV Doses (He/cm2) 1 x 1014-1017 Current (nA) 270 – 280 120 - 212 Time (h) 1 - 15 Dpa 0.08 – 0.8 0.07 – 0.7 Ion range (µm) ~ 1 ~ 3 Positron range Schematics of implanted sample PA TDS TRIM calculation for 1 x 1015 He/cm2

Experimental Techniques Thermal desorption spectroscopy Annealing from 300 K to 1500 K Heating rate of 0.33 K/sec Vacuum of 10-8 Torr Positron Beam Doppler Broadening In situ annealing with similar annealing rate to TDS Annealing duration of 5 min Oven cooling Measurement at room temperature

Results He implantations 500 keV & 2 MeV RT, 1014-1017 He/cm2

Implantation Current (µA) VEP 500 keV and 2 MeV, 1014-17 He/cm2 Positron range Implantation Current (µA) Dose (He/cm2) 500 keV 2 MeV 1014 0.12 0.31 1015 0.28 1016 0.27 0.21 1017 1.63 2.56

VEP - 500 keV and 2 MeV, 1014-17 He/cm2 Annealing study 500 keV Increase of S parameter with increasing dose  Dose effect !!! Similar behaviour not only within same implantation energy but also comparing both energies 500 keV VEP – decrease of S for 1017 He/cm2 Not observed in annealing study

TDS – 500 keV & 2 MeV Helium release

TDS – 500 keV & 2 MeV retention: 25-80% retention: 75-110%

Interpretation of results Example: 500 KeV, 1016 He/cm2 Overnight bake out Below 300 K Interstitial He is mobile below RT 300 K HELIUM IMPLANTATION

Interpretation of results 500 KeV, 1016 He/cm2 He in substitutional position Vacancy assisted diffusion of He Annealing of vacancies and vacancies clusters 1 µm

Interpretation of results 500 KeV, 1016 He/cm2 Dissociation of overpressured HenVm (n < m) clusters Possible re-trapping of He Formation of bigger clusters Stability of S level mainly due to HeV and stable HenVm pairs 1 µm

Interpretation of results 500 KeV, 1016 He/cm2 Ostwald ripening – formation of bubbles Increase of S for deeper implantation region Smaller diffusion length of He before retraping Dissociation of HeV pairs Phase transition of Eurofer97 (1160 K) 1 µm

Interpretation of results 500 KeV, 1016 He/cm2 Release of He from bubbles Dissociation vs. Migration mechanism 1 µm

Interpretation of results Overall picture

Final remarks Higher implantation dose leads to an increase in the S parameter Also observed in the positron annealing study Repetition of implantation 500 keV, 1017 He/cm2 necessary Similar TDS spectra shape for all doses Increasing He release up to 1500 K Phase transition/HeV dissociation in the range 1100 – 1200 K Peak on the left of the phase transition peak Helium release mechanisms are identified

Future work Continuation of He implantations Desorption experiments He implanted samples Neutron irradiated samples TEM Correlation of microstructure and mechanical properties