Hydrogen isotope retention and release in beryllium: The full picture from experiment and ab initio calculations
|
|
- Myra Craig
- 5 years ago
- Views:
Transcription
1 Member of the Helmholtz Association Hydrogen isotope retention and release in beryllium: The full picture from experiment and ab initio calculations Christian Linsmeier With contributions from: A. Allouche, M. Oberkofler, M. Reinelt, R. Piechoczek, J. Brinkmann Forschungszentrum Jülich Institut für Energie- und Klimaforschung Plasmaphysik
2 Overview 1. Wall materials and particle loads 2. Retention mechanisms 3. Retention and thermal release: results 4. Lattice orientation: single vs. polycrystal 5. Outlook: Neutron-induced defects Multi-component materials 6. Conclusions
3 Materials in ITER and DEMO
4 ITER first wall Fusion power: 500 MW Plasma volume: 840 m 3 Plasma current: 15 MA Typical density: m -3 Typical temperature: 20 kev Beryllium 700 m 2 beryllium first wall 100 m 2 tungsten divertor Tungsten 50 m 2 CFC strike point Carbon
5 First wall loads: particle energy ASDEX Upgrade conditions
6 D retention in beryllium [Anderl 1999] Be: ~700 m 2 D,T Variation by 1-2 orders of magnitude!
7 Hydrogen in Be: saturation D retention [D/m 2 ] D ions -> Be 1000 ev, T irr = 300 K (Haasz and Davis, 1997) 1000 ev, T irr = 373 K (Alimov and Roth, 2006) 200 ev, T irr = 323 K (Alimov and Roth, 2006) 1000 ev, T irr = 300 K (Reinelt and Linsmeier, 2009) D retention demonstrates saturation. For 1 kev D ion irradiation, the saturation is observed at a fluence of D/m 2. For D is trapped in the implantation zone with negligible diffusion into the bulk Incident fluence [D/m 2 ] High fluence experiments D retention [D/m 2 ] When the irradiation temperature increases, the D retention decreases ev - TPE (Causey et al. 1997) 100 ev - PISCES-B (Doerner et al. 1997) Exposure temperature [K] From review of R. Anderl et al., J. Nucl. Mater. 273 (1999) 1
8 Strategy Possible reasons for quantitative uncertainties: undefined BeO coverage undefined crystal structure unclear retention mechanisms Need for well-defined experiments and theory! To be resolved: retention in pure Be influence of crystal structure/orientation influence of surface oxide retention and release mechanisms
9 Experimental concept QMS desorption rate Be poly,be(0001), Be(11-20) D implantation (mass and energy separated) TPD Temperature Programmed Desorption NRA 3 He(d,p) 4 He Sequential release of D Limited by combination of bulk + surface processes Energy barriers for... Diffusion Detrapping Recombination Retention mechanisms Hydrogen retention
10 Surface morphology
11 Annealing SEM (1120) T 1000 K, several hours: Formation of Be crystallites Substantial material transport Recrystallization to low indexed facets
12 Annealing sputtering cycles AFM 500 nm Cycles of Cleaning D Implantation Degassing 1000 K Recrystallization Erosion D-induced structural modifications
13 Erosion: orientation-dependent SE EBSD 100 μm Be PC + D shows crystallites with less damage... more damage Red White Black = Basal plane surface FAST diffusion to surface = Basal plane surface SLOW diffusion to surface = Not indexed
14 Retention and release mechanisms
15 Hydrogen isotope inventory Main mechanisms for retention Implantation and release Diffusion Desorption
16 Implantation Simulation of collision cascade with Monte Carlo codes (TRIM) Binary collision approximation Energy loss: stopping Creation of displaced atoms and vacancies Projectile is trapped Result: Depth profile Deuterium in polycrystalline beryllium Depth profile measured with 10 MeV 28 Si
17 Thermal release Elementary steps diffusion of H in the solid trapping and release of H from binding sites (defects) recombination and desorption of H 2 from the surface
18 Thermal release Described by Diffusion-Trapping Model Local elementary reactions (trapping / release of H) thermally activated processes with: n i : number density of each species k: reaction rate constant E a : activation energy Diffusion: driven by concentration gradient (1st Fick s law) local concentration change: Diffusion described by continuity equation (2nd Fick s law)
19 Particle flux at desorption Partial differential equation: considers both diffusion and elementary reactions Source Sink Example: n i : concentration of mobile (dissolved) H mobil R: rates for trapping and release at traps PDE describes H diffusion and the reaction: Consider arbitrary elementary reactions Description of the thermal release by a system of coupled differential equations
20 D retention
21 Saturation of retention Trapping of D at ion-induced defects Reemission above 25 at.% low fluence linear high fluence saturation (D/Be) max =const Be ion range Implantation: D at 1 kev into Be (1120)
22 Saturation of retention Trapping of D at ion-induced defects Reemission above 25 at.% Retention within ion range Low inventory in main wall of ITER (D/Be) max =const Be ion range Γ = D cm -2 Γ = D cm -2 Retained fraction Retained fraction Be(1120) Be poly Implantation energy [kev] Be(1120) - Be poly Implantation energy [kev]
23 Saturation of retention Trapping of D at ion-induced defects Reemission above 25 at.% Retention within ion range Low inventory in main wall of ITER Annihilation of traps at grain boundaries Anisotropic diffusion of interstitials (DFT) Γ = D cm -2 Γ = D cm -2 Retained fraction Retained fraction Be(1120) Be poly Implantation energy [kev] Be(1120) - Be poly Implantation energy [kev]
24 Thermal release
25 Trapping sites and desorption stages Temperature-programmed desorption spectra Desorption rate [a.u.] Be poly, E Impl =1 kev ITER main wall bake-out temperature Fluence [10 16 cm -2 ] Temperature [K] 2.5
26 Trapping sites and desorption stages Temperature-programmed desorption spectra Desorption rate [a.u.] Be poly, E Impl =1 kev Retention in the structural modifications [%] Fluence [10 16 cm -2 ] Temperature [K] Sample saturation Incident fluence [10 15 D cm -2 ]
27 Saturation: Simulation by SDTrim.SP Depth [nm] Retention in structural modifications [%] Supersaturation SDTrim.SP Calculation Incident fluence [10 15 D cm -2 ] 10 TPD Experiments Incident fluence [10 15 D cm -2 ] D Concentration (cut off) Bulk saturation concentration: 26 at% D Concentration build-up in a depth of 40 nm Supersaturation Structural modifications
28 Trapping sites and desorption stages Desorption rate [a.u.] Temperature-programmed desorption spectra Be poly, E Impl =1 kev Fluence [10 16 cm -2 ] Stable structures from density functional theory (DFT) calculations by A. Allouche Amorphous BeH 2-x Temperature [K] 2.5
29 Trapping sites and desorption stages Temperature-programmed desorption spectra Stable structures from density functional theory (DFT) calculations by A. Allouche Be poly, E Impl =1 kev Fluence [10 16 cm -2 ] Desorption rate [a.u.] Temperature [K] H Amorphous BeH 2-x Position of H inside a monovacancy
30 Modelling the release at low fluences Desorption flux [10 13 cm -2 s -1 ] Implantation energy 1 kev 3 kev - Be (1120) 2.7 * D cm Temperature [K] n t mob Reaction-diffusion equation n = D x x mob act E + R source/ sink Single processes not accessible in experiments Density functional theory Solve set of coupled differential equations numerically Reproduce both spectra (different initial conditions) with identical set of parameters
31 Modelling the release at low fluences Desorption flux [10 13 cm -2 s -1 ] Implantation energy 1 kev 3 kev - Be (1120) 2.7 * D cm Temperature [K] Model 1: static traps diffusion barrier from literature adapted barrier for detrapping Implemented processes: - diffusion of D E act = 0.3 ev - trapping E act = 0.3 ev D mob + trap D trap - detrapping E act = 1.9 ev D trap D mob + trap Shift with initial depth due to effective diffusion Assumed missing physics: Annealing of defects Simulated peaks broader than experiment! Implement trap mobility
32 Desorption flux [10 13 cm -2 s -1 ] Modelling the release at low fluences Implantation energy 1 kev 3 kev - Be (1120) 2.7 * D cm Temperature [K] Forward calculations yield Shift with initial depth profile Peak width Assymmetry Model 2: Assumption of trapping at single vacancies consistent with experimental desorption spectra trapping at mobile vacancies accumulation of D mob at D trap diffusion barriers from DFT adapted barrier for detrapping Implemented processes: - diffusion of vac E act = 0.70 ev - diffusion ( ) of D E act = 0.41 ev - trapping E act = 0.41 ev D mob + vac D trap - accumulation E act = 0.41 ev D mob + D trap 2 D trap - detrapping E act = 1.86 ev D trap D mob + vac (1.7 ev)
33 Lattice orientation
34 D diffusion in beryllium Be crystal lattice Be(0001) plane ǁ to surface Be(11-20) plane to surface Beryllium has not an ideal hcp structure. Be-Be distances are closer in <0001> than perpendicular to it (e.g. <11-20>) DFT (Density Functional Theory) calculations show anisotropy in transport processes with respect to Be basal planes
35 Modeling: 2D coupled rate equations Strategy Solve a coupled reaction diffusion system (CRDS) consisting of an arbitrary number of diffusing species i=a,b,c in 1, 2 or 3 dimensions Solve system of partial differential equations for the time dependent 2D depth profile ρ(x,z,t) [m -3 ] A(, xzt,) A(, xzt,) A(, xzt,) Dx( Tt ( )) Dz( Tt ( )) t x x z z ( ) ( ) ( xzt,, ) E 1 Γ = 1( A, ρb, t) k1ρ AρB exp kbt ( t) Form Annihilation Source i ABC,,... i ABC,,... i A + B C C A+ B ρ 2 Γ 2( ρc, t) = k2ρc exp B E ktt ()
36 TPD of D implanted in Be single crystals Surface desorption flux [10 17 D m -2 s -1 ] 2,5 2,0 1,5 Circles: Experiment Lines: 2D CRDS Model Be (11-20) 1 kev/d 2.7 x D cm -2 Be (11-20) 3 kev D 2.9 x D cm -2 Be (0001) 3 kev D 2.7 x D cm -2 1,0 0,5 0, Temperature [K] TPD spectra and 2D-CRDS simulations after implantation of D at 1 kev/d and 3 kev/d in Be(0001) and Be(11-20) Only one type of trap! R. Piechoczek et al., J. Nucl. Mater. 438 (2013) S Desorption temperature shift for different implantation energies 2. Desorption temperature shift for Be(0001) and Be(11-20) 3. Less D retention in Be(0001) than in Be(11-20) 1. Deeper implantation longer diffusion path to the surface higher TPD peak temperature 2. Anisotropy of Be lattice 2D anisotropic modelling required to implement results from DFT calculations 3. Dynamics during D implantation (MV+SI annihilation and trapping in MV) determines retention
37 Simulation phases 1000 Temperature [K] Implantation Relaxation Heating Time [s]
38 Simulation phases Surface flux [m -2 s -1 ] Surface flux [m -2 s -1 ] 1E20 1E18 1E16 2D-CRDS Simulation Be [11-20] Mono vacancies Be self interstitials Hydrogen E E20 2D-CRDS Simulation Time [s] Be [0001] E18 1E16 Mono vacancies Be self interstitials Hydrogen E Time [s] Temperature [K] Temperature [K] self interstitials during implantation mono vacancies stable after implantation, thermally instable self interstitials during implantation mono vacancies vanish quickly
39 TPD from Be polycrystal Identical parameters also applied for polycrystalline Be Be(11-20) Be(0001) 50 μm SEM (EBSD) Shift for Be poly reproduced with no retrapping: fast grain boundary diffusion heating ramp variation reproduced: no (self)trapping during heating Surface desorption flux [10 17 D m -2 s -1 ] Symbol: Experiment Poly crystal, 3keV/D, 2.0 K/s Lines: 2D CRDS Model [11-20] With re-trapping [0001] With re-trapping [11-20] No re-trapping [0001] No re-trapping Surface desorption flux [10 17 D m -2 s -1 ] Symbols: Experiment Lines: 2D CRDS Model 0.1 K/s 0.2 K/s 0.7 K/s 2.0 K/s Temperature [K] Temperature [K] R. Piechoczek et al., J. Nucl. Mater. 438 (2013) S1072
40 Parameters for D release and diffusion Experimentally and DFT determined parameters for full description Basal Plane Basal Plane Diffusivity Diffusivity ν ΔE act [ev] ΔE act [ev] CRDS CRDS DFT [Allouche] Mobile Hydrogen H mob 3.11E-06 <0.4* 0.2 Mono vacancy MV 3.11E Self interstitial SI 3.11E Trapped Hydrogen H trap - - H mob 7.68E-06 <0.4* 0.4 MV 7.68E SI 7.68E H trap - - Trapping H mob + MV H trap 1.00E Detrapping H trap H mob + MV 1.00E+11* Annihilation MV + SI E Self trapping H mob + 1 H trap 2 H trap + SI 1.00E Anisotropy in diffusion of self-interstitials crucial for modeling! R. Piechoczek et al., J. Nucl. Mater. 438 (2013) S1072
41 Surface oxide
42 Be with oxide layer Composition of first atomic layer: Ion scattering spectroscopy! (45, 500 ev He + ) Be + 3 ML BeO (closed surface layer) Be terminated surface + 3 ML BeO (covered) Segregation of Be at the surface Annealing (1000 K): Be-terminated surface (desorption via pure Be surface) No annealing: TPD via BeO covered surface
43 TPD: Influence of BeO-coverage desprtion rate [a.u.] 3.0 ML BeO 0.2 ML BeO BeO:D (surface) temperature [K] No change of E A of release from binding states No recombination limit Trapping in the bulk time [s] Formation of BeO:D at the surface
44 Implantation at elevated temperatures BeD 2 BeO:D (surface) Ion induced trap sites unaffected new trapping sites appear (deuteride, surface oxide) BeD 2 formation (decomposition >570 K) retention at 530 K: 90%, instead of expected 70% 320 K 530 K M. Reinelt et al., New J. Phys. 11 (2009)
45 Implantation into BeO Implantation of D within BeO layer changes D release: small amount of low-t trapping D release over wide temperature range only 75% of total D released until 850 K only small fraction of total D released until 513 K (ITER wall bake-out) Similar total retained D amounts M. Oberkofler et al., J. Nucl. Mater. 415 (2011) S724
46 Influence of neutron damage
47 Neutron-induced trap formation: Tungsten Damage simulation Example: Trapping in heavy-ion damage at rear surface Deuterium depth profiles measured on the front and rear side of W samples Damaged either by 20 MeV W ions The front side was exposed to D plasma to a fluence of D/m 2 at 550 K D retention decorates damage profiles, but also demonstrates long range damaging beyond ion range B. Tyburska et al., J. Nucl. Mater. 415 (2011) S680
48 Neutron-induced trap filling in ITER Trap density, at.% Modelling of ITER wall conditions Damage evolution: 10-7 dpa/s (from ITER Org.) saturation trap density 1% ev, I 0 =10 21 D/m 2 s, T=500 K plasma-induced defects n-induced defects 0.0 1x x x x x x10 2 Fluence (D/m 2 ) D concentration (at.%.) Diffusion and trap filling: Diffusive trap filling using established diffusion coefficient D/m D/m D/m D/m Filling of 1 mm W armour in about 3 years steady state operation Relevant to DEMO rather than ITER 60 ev, I 0 =10 21 D/m 2 s, T=500 K with n-generated traps without n-generated traps 0, Depth (µm) O. Ogorodnikova et al., J. Nucl. Mater. 415 (2011) S661
49 Multi-component materials
50 DEMO first wall: W alloy Power plant conceptual study Temperature profile in PPCS Model A, 10 days after accident with a total loss of all coolant. [Final Report of the European Fusion Power Plant Conceptual Study, 2004] Accidental loss of coolant: peak temperatures of first wall up to 1200 C due to nuclear afterheat Additional air ingress: formation of highly volatile WO 3 (Re, Os) Evaporation rate: order of kg/h at >1000 C in a reactor (1000 m 2 surface) large fraction of radioactive WO 3 may leave hot vessel Development of selfpassivating tungsten alloys
51 DEMO first wall: W alloy Rate [ m 2 / t [mg 2 /sec]] K W-Cr binary ~0.5% Ti, TGA 1273 K Chromium concentration [wt-%] W-Cr-Ti self-passivating alloy Optimum Cr concentration Ti active element: reduce oxidation rate at high T Ti: hydrogen retention?
52 W-Cr-Ti: D retention D depth profiles room temp. loading 100 V bias 3 He NRA depth profiles almost homogeneous D distribution D content vs. Ti fraction linear dependence 2 at-% threshold TiH 2? Replace Ti by non-hydride former!
53 Summary Hydrogen retention and release from beryllium Retention and release mechanisms identified and quantified ITER: Tritium retention in metallic Be only within ion range (small inventory) Release < 500 K: BeD 2-x supersaturated Be-D, D fraction ~0.25 Release > 500 K: vacancies, ion-induced traps Essential mechanisms: - effective diffusion - mobility of vacancies - accumulation of D in vacancies BeO Thin (several ML) oxide: not rate-limiting for release Different mechanisms than for Be Only 75% D released <850 K
54 Outlook DEMO first wall: neutrons and alloys Neutron wall loads: additional traps, deeper than for ion-induced defects DEMO PFM: most probably not a pure metal, but alloy New diffusion, retention and release mechanisms DFT data missing! Improve ability to deal with large unit cells
Fundamental aspects of beryllium compound formation and erosion and hydrogen retention in beryllium
Fundamental aspects of beryllium compound formation and erosion and hydrogen retention in beryllium Christian Linsmeier P. Goldstraß, A. Wiltner, F. Kost, M. Reinelt, M. Oberkofler, M. Köppen, R. Piechoczek
More informationH isotope retention in Be and Be mixed materials
Max-Planck-Institut für Plasmaphysik IAEA 2011 H isotope retention in Be and Be mixed materials Wolfgang Jacob IPP Plasma Edge and Wall Division IAEA CRP meeting, W. Jacob, May 2011 1 Introduction: Challenges
More informationDetermination of binding energies for hydrogen with radiation defects in tungsten by means of TDS: theory and experimental data
National Research Nuclear University MEPHI (Moscow Engineering and Physics Institute) Russia, Moscow Plasma physics department Determination of binding energies for hydrogen with radiation defects in tungsten
More informationErosion, formation of deposited layers and fuel retention for beryllium under the influence of plasma impurities
Erosion, formation of deposited layers and fuel retention for beryllium under the influence of plasma impurities A. Kreter 1, T. Dittmar 1,2, D. Nishijima 2, R.P. Doerner 2, M.J. Baldwin 2 and K. Schmid
More informationCharacterization and erosion of metal-containing carbon layers
Characterization and erosion of metal-containing carbon layers Martin Balden Max-Planck-Institut für Plasmaphysik, EURATOM Association, D-85748 Garching, Germany Materials Research Division (MF) Outline
More informationDeuterium retention mechanism in tungsten-coatings exposed to JT-60U divertor plasmas
1 EXD/P3-10 Deuterium retention mechanism in tungsten-coatings exposed to JT-60U divertor plasmas M. Fukumoto 1), T. Nakano 1), K. Itami 1), T. Wada 2), Y. Ueda 2), T. Tanabe3) 1) Japan Atomic Energy Agency,
More informationThomas Schwarz-Selinger. recombination, implantation, diffusion and release
Max-Planck-Institut für Plasmaphysik Thomas Schwarz-Selinger recombination, implantation, diffusion and release heat load issues Recombination coefficient Recombination coefficient for hydrogen in stainless
More informationEffects of D and He Implantation Depth on D Retention in Tungsten Under
Effects of D and He Implantation Depth on D Retention in Tungsten Under Simultaneous D-He Ion Irradiation T.J. Finlay 1, J.W. Davis 1, K. Sugiyama 2, V.Kh. Alimov 3, A.A. Haasz 1 1 University of Toronto
More informationHydrogen isotope retention in W irradiated by heavy ions and helium plasma
Hydrogen isotope retention in W irradiated by heavy ions and helium plasma M. Sakamoto, H. Tanaka, S. Ino, H. Watanabe 1, M. Tokitani 2, R. Ohyama 3, A. Rusinov 3 and N. Yoshida 1 Plasma Research Center,
More informationIT/P1-20 Beryllium containing plasma interactions with ITER materials
IT/P1-2 Beryllium containing plasma interactions with ITER materials R.P. Doerner 1), M. Baldwin 1), G. Federici 2), J. Hanna 1), A. Loarte 2), D. Nishijima 1), R. Pugno 3), J. Roth 3), K. Schmid 3), G.
More informationImpacts of Carbon Impurity in Plasmas on Tungsten First Wall
1 Impacts of Carbon Impurity in Plasmas on First Wall Y. Ueda, T. Shimada, M. Nishikawa Graduate School of Engineering, Osaka University, 2-1 Yamadaoka, Suita, Osaka 565-0871, Japan e-mail contact of main
More informationExperimental possibilities in Jülich an update
Experimental possibilities in Jülich an update 15 th June 2016 M. Köppen A. Allouche, F. Aumayr, D. Borodin, J. Bröder, T. Dittmar, K. Dobes, P. Dollase, J. Du, Y. Ferro, A. Kreter, J. Linke, Ch. Linsmeier,
More informationDevelopments at IPP regarding sputtering of EUROFER
Max-Planck-Institut für Plasmaphysik Developments at IPP regarding sputtering of EUROFER W. Jacob, K. Sugiyama, M. Balden, M. Oberkofler, T. Schwarz-Selinger, R. Arredondo, M. Reisner, S. Elgeti Max-Planck-Institut
More informationEstimations of erosion fluxes, material deposition and tritium retention in the divertor of ITER
Estimations of erosion fluxes, material deposition and tritium retention in the divertor of ITER A. Kirschner a *, D. Borodin a, V. Philipps a, U.Samm a, R. Ding a, K. Schmid b, J. Roth b, A. Kukushkin
More informationThe influence of radiation damage on D retention in W: IPP activities
The influence of radiation damage on D retention in W: IPP activities W. Jacob, M. Mayer, T. Schwarz-Selinger, J. Bauer Max-Planck-Institut für Plasmaphysik, 85748 Garching, Germany L. Ciupinski, J. Grzonka
More informationInfluence of beryllium carbide formation on deuterium retention and release
Influence of beryllium carbide formation on deuterium retention and release C. Porosnicu a *, A. Anghel a, K. Sugiyama b, K. Krieger b, J. Roth b, C. P. Lungu a a National Institute for Laser, Plasma and
More informationComparison of hydrogen retention in W and W/Ta alloys
Comparison of hydrogen retention in W and W/Ta alloys K. Schmid, V. Rieger, A. Manhard Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstraße 2, D-85748 Garching b. München Germany
More informationHydrogen in Tungsten as Plasma-facing Material
Hydrogen in Tungsten as Plasma-facing Material Joachim Roth, Klaus Schmid Max-Planck-Institut für Plasmaphysik, EURATOM-Association, 85748 Garching, Germany Abstract: Materials facing plasmas in fusion
More informationInfluence of the Microstructure on the Deuterium Retention in Tungsten
Influence of the Microstructure on the Deuterium Retention in Tungsten A. Manhard,a K. Schmid, a M. Balden a W. Jacob a a Max-Planck-Institut für Plasmaphysik, Boltzmannstraße 2, D-85748 Garching b. München,
More informationPlasma interactions with Be surfaces
Plasma interactions with Be surfaces P. Doerner for members of the Team Center for Energy Research, University of California San Diego, USA Work performed as part of: US-EU Collaboration on Mixed-Material
More informationMulti-Component Plasma Interactions with Elemental and Mixed-Material Surfaces
1 EXD/P3-08 Multi-Component Plasma Interactions with Elemental and Mixed-Material Surfaces R. P. Doerner 1), M. J. Baldwin 1), A. Kreter 2), M. Miyamoto 3), D. Nishijima 1), G. R. Tynan 1) and K. Umstadter
More informationThe Graduate University for Advanced Studies, Oroshi-cho, Toki , Japan 2
Bi-directional hydrogen isotopes permeation through a reduced activation ferritic steel alloy F82H (Effects of tungsten coatings on hydrogen isotopes permeation) Yue Xu 1 and Yoshi Hirooka 1,2 1 The Graduate
More informationPlasma wall interactions from a material perspective in fusion devices
Plasma wall interactions from a material perspective in fusion devices Presented by H.T. Lee Graduate School of Engineering,, Suita, Osaka, 565-0871, Japan With material generously supplied by K. Krieger,
More informationM. Short (MIT) F. A. Garner (REC) M. B. Toloczko (PNNL) L. Shao, T. Chen, J. Gigax, E. Aydogan, C.-C. Wei (TAMU) V. N.
Examination of issues involved when using ion irradiation to simulate void swelling and microstructural stability of ferritic-martensitic alloys in spallation environments M. Short (MIT) F. A. Garner (REC)
More informationPerformances of Helium, Neon and Argon Glow Discharges for Reduction of Fuel Hydrogen Retention in Tungsten, Stainless Steel and Graphite
1 FTP/P7-10 Performances of Helium, Neon and Argon Glow Discharges for Reduction of Fuel Hydrogen Retention in Tungsten, Stainless Steel and Graphite T. Hino 1), Y. Yamauchi1), Y. Kimura1), A. Matsumoto1),
More informationBeryllium containing plasma interactions with ITER materials
Beryllium containing plasma interactions with ITER materials R.P. Doerner 1), M. Baldwin 1), J. Hanna 1), Ch. Linsmeier 2), D. Nishijima 1), R. Pugno 2), J. Roth 2), K. Schmid 2) and A. Wiltner 2) 1) University
More informationVisco-elastic model of the fuzz growth (P64B)
Visco-elastic model of the fuzz growth (P64B) S. I. Krasheninnikov* University California San Diego, La Jolla, CA 92093, USA PACS numbers: 47.55.dd, 52.40.Hf Abstract The visco-elastic model of fuzz growth
More informationRecent Workshops - Tungsten PMI / PFC Work
Recent Workshops - Tungsten PMI / PFC Work D. Buchenauer, R. Kolasinski, and R. Causey 2009 Japan - US Workshop (3 workshops) US-Japan Workshop on Interaction between plasma and high Z material towards
More informationMulti-scale modeling of hydrogen transport in porous graphite
Multi-scale modeling of hydrogen transport in porous graphite Ralf Schneider Computational Science Institute of Physics Ernst-Moritz-Arndt Universität, Greifswald 12.12.2011 Hydrocarbon-codeposition Emppu
More informationAuthor(s) Xu, Q.; Cao, X.Z.; Sato, K.; Yoshii. Citation Journal of Nuclear Materials (2012)
Title Effects of alloying elements on the Ni alloys Author(s) Xu, Q.; Cao, X.Z.; Sato, K.; Yoshii Citation Journal of Nuclear Materials (2012) Issue Date 2012-12 URL http://hdl.handle.net/2433/175277 Right
More informationMicroscopic Damage of Metals Exposed to the Helium Discharges in TRIAM-1M Tokamak and its Impact on Hydrogen Recycling Process
Microscopic Damage of Metals Exposed to the Helium Discharges in TRIAM-1M Tokamak and its Impact on Hydrogen Recycling Process FT/P1-16 N. Yoshida, M. Miyamoto, K. Tokunaga, H. Iwakiri, H. Wakimoto, T.
More informationImpact of hydrogen pick up and applied stress on c component loops: radiation induced growth of recrystallized zirconium alloys
Impact of hydrogen pick up and applied stress on c component loops: Toward a better understanding of the radiation induced growth of recrystallized zirconium alloys L. Tournadre 1, F. Onimus 1, J.L. Béchade
More informationRadiation damage of Heavy ions and H irradiated Tungsten Some Experimental Results
Radiation damage of Heavy ions and H irradiated Tungsten Some Experimental Results Presented by : P.M.Raole Institute for Plasma Research, Gandhinagar-382428, India Collaborators : P.N.Maya, Shishir Deshpande,
More informationNPTEL. Radiation damage and Radiation effects on Structural Materials - Video course. Metallurgy and Material Science.
NPTEL Syllabus Radiation damage and Radiation effects on Structural Materials - Video course COURSE OUTLINE Structural materials in a nuclear reactor are subjected to severe conditions of temperature and
More informationEffects of Plasma Interaction with Radiation-Damaged Tungsten
1 FTP/3-3Rb Effects of Plasma Interaction with Radiation-Damaged Tungsten V.S. Koidan 1), B.I. Khripunov 1), A.I. Ryazanov 1), A.N. Brukhanov 1), O.K.Chugunov 1), V.M. Gureev 1), S.N. Kornienko 1), B.V.Kuteev
More informationNeutron Flux Effects on Embrittlement in Reactor Pressure Vessel Steels
Neutron Flux Effects on Embrittlement in Reactor Pressure Vessel Steels R. E. Stoller Metals and Ceramics Division Oak Ridge National Laboratory Oak Ridge, TN 37831-6151 USA International Workshop Influence
More informationObject Kinetic Monte Carlo Simulations of Radiation Damage in Bulk Tungsten Part-II: With a PKA Spectrum Corresponding to 14-MeV Neutrons
Object Kinetic Monte Carlo Simulations of Radiation Damage in Bulk Tungsten Part-II: With a PKA Spectrum Corresponding to 14-MeV Neutrons Giridhar Nandipati a1, Wahyu Setyawan a, Howard L. Heinisch a,
More informationFeasibility Study on the Fast-Ignition Laser Fusion Reactor With a Dry Wall FALCON-D*
US/Japan Workshop on Power Plant Studies and Related Advanced Technologies 5-7 March 2008, UCSD Feasibility Study on the Fast-Ignition Laser Fusion Reactor With a Dry Wall FALCON-D* *) Fast-ignition Advanced
More informationExtended abstract High entropy alloys for fusion applications
Abstract Extended abstract High entropy alloys for fusion applications André Ruza andre.ruza@tecnico.ulisboa.pt In a tokamak, nuclear fusion reactor, the divertor is subjected to a high heat flux. Tungsten
More informationTransient events: Experiments in JUDITH (I and II) and modelling
Transient events: Experiments in JUDITH (I and II) and modelling O.V. Ogorodnikova, J. Compan, T. Hirai, J. Linke The electron beam test facility JUDITH I e-beam electron beam power: acceleration voltage:
More informationChemical Binding States of Carbon Atoms Migrated in Tungsten Coating Layer Exposed to JT-60U Divertor Plasmas
Chemical Binding States of Carbon Atoms Migrated in Tungsten Coating Layer Exposed to JT-60U Divertor Plasmas Masakatsu FUKUMOTO, Tomohide NAKANO, Yoshio UEDA 1) and Kiyoshi ITAMI Japan Atomic Energy Agency,
More informationM. R. Gilbert, S. L. Dudarev, S. Zheng, L. W. Packer, and J.-Ch. Sublet. EURATOM/CCFE Fusion Association, UK
Integrated computational study of material lifetime in a fusion reactor environment M. R. Gilbert, S. L. Dudarev, S. Zheng, L.. Packer, and J.-Ch. Sublet EURATOM/CCFE Fusion Association, UK October 12,
More informationNeutron Irradiation Effects on Grain-refined W and W-alloys
25th IAEA Fusion Energy Conference 13 18 October 2014 Saint Petersburg, Russian Federation MPT/1-4 Neutron Irradiation Effects on Grain-refined W and W-alloys A. Hasegawa a, M. Fukuda a, T. Tanno a,b,
More informationProspects of new ODS steels
Prospects of new ODS steels Annual Fusion Seminar VTT Tampere, June 2-3, 2010 Seppo Tähtinen VTT Technical Research Centre of Finland 6/3/2010 2 Fusion advantages Unlimited fuel No CO 2 or air pollution
More informationDiffusion behaviour of cesium in silicon carbide at T > 1000 C
Diffusion behaviour of cesium in silicon carbide at T > 1000 C E. Friedland (a)*, N.G. van der Berg (a), T.T. Hlatshwayo (a), R.J. Kuhudzai (a), J.B. Malherbe (a), E. Wendler (b), W. Wesch (b) (a) Physics
More informationStudy the interaction of RAFM steel with laboratory and EAST plasma conditions
First CRP meeting Plasma-wall Interaction with Reduced-activation Steel Surfaces in Fusion Devices Study the interaction of RAFM steel with laboratory and EAST plasma conditions Wang Peng, Qiao Li, Zhang
More informationAdvanced Materials. Christian Linsmeier. Forschungszentrum Jülich Institut für Energie- und Klimaforschung Plasmaphysik
Member of the Helmholtz Association Advanced Materials Christian Linsmeier Forschungszentrum Jülich Institut für Energie- und Klimaforschung Plasmaphysik Advanced materials Fiber-reinforced copper composites
More informationP. N. LEBEDEV PHYSICAL INSTITUTE OF THE RUSSIAN ACADEMY OF SCIENCES PREPRINT
P. N. LEBEDEV PHYSICAL INSTITUTE OF THE RUSSIAN ACADEMY OF SCIENCES PREPRINT 18 CHANNELING A.V. BAGULYA, O.D. DALKAROV, M.A. NEGODAEV, A.S. RUSETSKII, A.P. CHUBENKO, V.G. RALCHENKO, A.P. BOLSHAKOV EFFECT
More informationINDC International Nuclear Data Committee
International Atomic Energy Agency INDC(NDS)- 0632 Distr. LP,NE,SK INDC International Nuclear Data Committee Data for Erosion and Tritium Retention in Beryllium Plasma- Facing Materials Summary Report
More informationDeuterium Retention and Trapping in Polycrystalline Tungsten under Simultaneous Implantation of Deuterium with Helium and with Neon
Deuterium Retention and Trapping in Polycrystalline Tungsten under Simultaneous Implantation of Deuterium with Helium and with Neon by Tamara Jean Finlay A thesis submitted in conformity with the requirements
More informationSubject Index. grain size, 508 hardening, 490 helium transport to grain boundaries,
STP955-EB/Dec. 1987 Subject Index A Alloys (See under type of alloy) Aluminum cavities near grain boundaries, 220, 233 cold working, 508 copper-aluminum alloys, 14 defects introduced by proton irradiation,
More informationOverview of Fuel Inventory in JET with the ITER-Like Wall
Overview of Fuel Inventory in JET with the ITER-Like Wall Anna Widdowson E. Alves, A. Baron-Wiechec, N.P. Barradas, N. Catarino, J.P. Coad, V. Corregidor, K. Heinola, S. Koivuranta, S. Krat, A. Lahtinen,
More informationErosion and fuel retention of different RAFM steel grades
Erosion and fuel retention of different RAFM steel grades Peng Wang 1, Li Qiao 1, Liang Gao 2, Wolfgang Jacob 2, Engang Fu 3 1. Lanzhou Institute of Chemical Physics, Lanzhou, China 2. Max-Planck Institute
More informationStudies of Impurity Seeding and Divertor Power Handling in Fusion Reactor
1 FIP/P8-11 Studies of Impurity Seeding and Divertor Power Handling in Fusion Reactor K. Hoshino 1, N. Asakura 1, K. Shimizu 2 and S. Tokunaga 1 1 Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212
More informationErosion of Pyrolytic Graphite and Ti-doped Graphite due to High Flux Irradiation
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 34, No. 8, p. 792-798 (August 1997) Erosion of Pyrolytic Graphite and Ti-doped Graphite due to High Flux Irradiation Yusuke OHTSUKAt, Junpei OHASHI, Yoshio
More informationCOMPARISON OF STEADY-STATE AND PULSED-PLASMA TOKAMAK POWER PLANTS
COMPARISON OF STEADY-STATE AND PULSED-PLASMA TOKAMAK POWER PLANTS F. Najmabadi, University of California, San Diego and The ARIES Team IEA Workshop on Technological Aspects of Steady State Devices Max-Planck-Institut
More informationTrapping of Hydrogen at Irradiation Induced Defects
Trapping of Hydrogen at Irradiation Induced Defects B.F. Kammenzind, W.J. Duffin (Retired) Bechtel Marine Propulsion Corporation Bettis Laboratory Knolls Laboratory 18 th International Symposium on Zirconium
More informationLong-term fuel retention and release in JET ITER-Like Wall at ITER-relevant baking temperatures
EUROFUSION WPJET2-CP(16) 15435 K Heinola et al. Long-term fuel retention and release in JET ITER-Like Wall at ITER-relevant baking temperatures Preprint of Paper to be submitted for publication in Proceedings
More informationSimulation of Power Exhaust in Edge and Divertor of the SlimCS Tokamak Demo Reactor
J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Simulation of Power Exhaust in Edge and Divertor of the SlimCS Tokamak Demo Reactor Nobuyuki ASAKURA, Katsuhiro SHIMIZU, Hisato KAWASHIMA, Kenji TOBITA and Tomonori
More informationDeuterium retention in tungsten films deposited by magnetron sputtering
Deuterium retention in tungsten films deposited by magnetron sputtering P. Wang, W. Jacob, L. Gao, S. Elgeti (Lindig), M. Balden Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstr.
More informationin tungsten shosse 31, Moscow, Russia recrystallized W sample by low fluences of 10 kev/d ions, its annealing, and subsequent lowenergy
Published in: J. Nucl. Mater., http://dx.doi.org/10.1016/j.jnucmat.2016.04.052 Experimental determination of the deuterium binding energy with vacancies in tungsten M. Zibrov a,b,c, S. Ryabtsev a, Yu.
More informationImperfections: Good or Bad? Structural imperfections (defects) Compositional imperfections (impurities)
Imperfections: Good or Bad? Structural imperfections (defects) Compositional imperfections (impurities) 1 Structural Imperfections A perfect crystal has the lowest internal energy E Above absolute zero
More informationASTM Conference, May , Hilton Head Island, SC
ASTM Conference, May 17 2016, Hilton Head Island, SC Understanding Irradiation Growth through Atomistic Simulations: Defect Diffusion and Clustering in Alpha-Zirconium and the Influence of Alloying Elements
More informationNumerical Study on the Ablation Effects of Tungsten Irradiated by High-intensity Pulsed Ion Beam
Physics Procedia (011) 46 51 011 International Conference on Physics Science and Technology (ICPST 011) Numerical Study on the Ablation Effects of Tungsten Irradiated by High-intensity Pulsed Ion Beam
More informationTungsten as First Wall Material in ASDEX Upgrade. The Implications of a High-Z First Wall Materials on the Noble Gas Wall Recycling
ASDEX Upgrade Max-Planck-Institut für Plasmaphysik Tungsten as First Wall Material in ASDEX Upgrade R. Dux, R.Neu, V. Bobkov, H. Greuner, O. Gruber, A. Herrmann, A. Kallenbach, C. Maggi, T. Pütterich,
More informationNuclear Fuel Engineering (2. Modeling) Department of Nuclear Eng. KHU Kwnagheon Park
Nuclear Fuel Engineering (2. Modeling) Department of Nuclear Eng. KHU Kwnagheon Park 2. Behaviors of Pellet during Normal Operation 2 2.1. Temperature Distribution in a Fuel Rod C p T t kt q ''' ( r) Macroscopic
More informationTexture Evolution during Casting and Hot Rolling of a β-ti-nb alloy
Max-Planck-Institut für Eisenforschung, Düsseldorf Texture Evolution during Casting and Hot Rolling of a β-ti-nb alloy B. Sander, D. Ma, M. Friak, J. Neugebauer, D. Raabe International Conference on the
More informationStudies of Hydrogen Isotope Accumulation in Plasma Facing Materials Performed in Kurchatov Institute
EX/P4- Studies of Hydrogen Isotope Accumulation in Plasma Facing Materials Performed in Kurchatov Institute B.N. Kolbasov ), M.I. Guseva ), L.N. Khimchenko ), B.I. Khripunov ), P.V. Romanov 2), V.G. Stankevich
More informationPhase Transformation of Materials
2009 fall Phase Transformation of Materials 10.08.2009 Eun Soo Park Office: 33-316 Telephone: 880-7221 Email: espark@snu.ac.kr Office hours: by an appointment 1 Contents for previous class Interstitial
More informationChemical erosion by deuterium impact on carbon films doped with nanometre-sized carbide crystallites
Chemical erosion by deuterium impact on carbon films doped with nanometre-sized carbide crystallites M. Balden*, C. Adelhelm, E. de Juan Pardo, J. Roth Max-Planck-Institut für Plasmaphysik, EURATOM Association,
More informationMicroscopic Damage of Tungsten and Molybdenum Exposed to Low-Energy Helium Ions
Plasma Science and Technology, Vol.17, No.4, Apr. 2015 Microscopic Damage of Tungsten and Molybdenum Exposed to Low-Energy Helium Ions FAN Hongyu ( ) 1,3, YANG Qi ( ) 1,3,LIXin( ) 1,3, NI Weiyuan ( ) 1,3,NIUJinhai(
More informationMICROSTRUCTURAL EVOLUTION IN CERIUM DIOXIDE IRRADIATED WITH HEAVY IONS AT HIGH TEMPERATURE
MICROSTRUCTURAL EVOLUTION IN CERIUM DIOXIDE IRRADIATED WITH HEAVY IONS AT HIGH TEMPERATURE Takeshi Mihara, Department of Nuclear Engineering and Management School of Engineering The University of Tokyo
More informationDamage buildup in GaN under ion bombardment
PHYSICAL REVIEW B VOLUME 62, NUMBER 11 15 SEPTEMBER 2000-I Damage buildup in GaN under ion bombardment S. O. Kucheyev,* J. S. Williams, and C. Jagadish Department of Electronic Materials Engineering, Research
More informationINDC International Nuclear Data Committee
International Atomic Energy Agency INDC(NDS)- 0592 Distr. LP,NE,SK INDC International Nuclear Data Committee Data Needs for Erosion and Tritium Retention in Beryllium Surfaces Summary Report of the Consultants
More informationDefects and Diffusion
Defects and Diffusion Goals for the Unit Recognize various imperfections in crystals Point imperfections Impurities Line, surface and bulk imperfections Define various diffusion mechanisms Identify factors
More information1. Introduction. What is implantation? Advantages
Ion implantation Contents 1. Introduction 2. Ion range 3. implantation profiles 4. ion channeling 5. ion implantation-induced damage 6. annealing behavior of the damage 7. process consideration 8. comparison
More informationImprovement of Thermal Shock Resistance of Isotropic Graphite by Ti-doping
Improvement of Thermal Shock Resistance of Isotropic Graphite by Ti-doping I. López-Galilea 1*, N. Ordás 1, C. García-Rosales 1, S. Lindig 2 1 CEIT and Tecnun (University of Navarra), 20018 San Sebastian,
More informationInstallation of a Plasmatron at the Belgian Nuclear Research Centre and its Use for Plasma-Wall Interaction Studies
1 Installation of a Plasmatron at the Belgian Nuclear Research Centre and its Use for Plasma-Wall Interaction Studies I. Uytdenhouwen (1, 2), J. Schuurmans (1), M. Decréton (1), V. Massaut (1) and G. Van
More informationPEER REVIEW FILE. Reviewers' Comments: Reviewer #1 (Remarks to the Author):
PEER REVIEW FILE Reviewers' Comments: Reviewer #1 (Remarks to the Author): The experimental results presented in the manuscript and the supplementary material is very convincing as they are based on in-situ
More informationIrradiation Damage Mechanism of Reactor Pressure Vessel Materials in PWR Nuclear Power Plant
2017 Asia-Pacific Engineering and Technology Conference (APETC 2017) ISBN: 978-1-60595-443-1 Irradiation Damage Mechanism of Reactor Pressure Vessel Materials in PWR Nuclear Power Plant Zhenguo Zhang,
More informationHydrogen isotopes permeation through the tungsten-coated F82H first wall
Hydrogen isotopes permeation through the tungsten-coated F82H first wall Presented at the IAEA-CRP meeting Oct. 16 th ~Oct.18 th, 2017 International Center, Vienna, Austria Yoshi Hirooka 1,2 and Yue Xu
More informationSection 4: Thermal Oxidation. Jaeger Chapter 3. EE143 - Ali Javey
Section 4: Thermal Oxidation Jaeger Chapter 3 Properties of O Thermal O is amorphous. Weight Density =.0 gm/cm 3 Molecular Density =.3E molecules/cm 3 O Crystalline O [Quartz] =.65 gm/cm 3 (1) Excellent
More informationCHAPTER 4: Oxidation. Chapter 4 1. Oxidation of silicon is an important process in VLSI. The typical roles of SiO 2 are:
Chapter 4 1 CHAPTER 4: Oxidation Oxidation of silicon is an important process in VLSI. The typical roles of SiO 2 are: 1. mask against implant or diffusion of dopant into silicon 2. surface passivation
More informationProject III. 4: THIN FILM DEVICES FOR LARGE AREA ELECTRONICS
Project III. 4: THIN FILM DEVICES FOR LARGE AREA ELECTRONICS Project leader: Dr D.N. Kouvatsos Collaborating researchers from other projects: Dr D. Davazoglou Ph.D. candidates: M. Exarchos, L. Michalas
More informationDiffusion of Fission Products through Silicon Carbide
AP/P5-03 Diffusion of Fission Products through Silicon Carbide E. Friedland 1, N.G. van der Berg 1, J.B. Malherbe 1, J.J. Hancke 2, J. Barry 2, E.Wendler 3, W.Wesch 3 1 Physics Department, University of
More informationCharacterization and erosion of metal-containing carbon films
Characterization and erosion of metal-containing carbon films M. Balden* and C. Adelhelm Max-Planck-Institut für Plasmaphysik, EURATOM Association, D-85748 Garching, Germany PACS: 28.52.Fa, 34.50.Dy, 79.20.Rf,
More informationSOLID SOLUTION METAL ALLOYS
SOLID SOLUTION METAL ALLOYS Synergy Effects vs. Segregation Phenomena D. Manova, J. Lutz, S. Mändl, H. Neumann 1 Table of Content Motivation Alloys vs. Pure Elements or Intermetallic Compounds Introduction
More informationPrevious Lecture. Vacuum & Plasma systems for. Dry etching
Previous Lecture Vacuum & Plasma systems for Dry etching Lecture 9: Evaporation & sputtering Objectives From this evaporation lecture you will learn: Evaporator system layout & parts Vapor pressure Crucible
More informationCHAPTERS SUMMARY OF RESULTS
CHAPTERS SUMMARY OF RESULTS Aluminium diffusion was investigated by NRA in five different semiconductors. Different experimental methods were employed. For in-diffusion investigation thin aluminium films
More informationCHAPTER 5: DIFFUSION IN SOLIDS
CHAPTER 5: DIFFUSION IN SOLIDS ISSUES TO ADDRESS... How does diffusion occur? Why is it an important part of processing? How can the rate of diffusion be predicted for some simple cases? How does diffusion
More informationPrometheus-L Reactor Building Layout
Prometheus-L Reactor Building Layout Two Main Options for the Final Optic (1) SiO 2 or CaF 2 wedges 85 40 cm stiff, lightweight, actively cooled, neutron transparent substrate 4.6 m (2) Grazing incidence
More informationModeling Radiation-Induced Segregation in Ferritic-Martensitic Steels
University of Tennessee, Knoxville Trace: Tennessee Research and Creative Exchange Masters Theses Graduate School 5-2015 Modeling Radiation-Induced Segregation in Ferritic-Martensitic Steels Aaron Patrick
More informationShort-range order and microhardness of the compositionally complex alloy Al 8 Co 17 Cr 17 Cu 8 Fe 17 Ni 33
Short-range order and microhardness of the compositionally complex alloy Al 8 Co 17 Cr 17 Cu 8 Fe 17 Ni 33 Andrea Fantin 1, Anna Manzoni 2, Tobias Scherb 2, Yao Liu 3, Gerhard Schumacher 1,2, John Banhart
More informationExamples of the use of XPS in Catalysis Research from the Vohs Group
Examples of the use of XPS in Catalysis Research from the Vohs Group Supported monolayer vanadia catalysts Ceria/zirconia automotive emissions control catalysts Reaction of oxygenates on Zn Pd/Zn methanol
More informationLow-Temperature Resistivity Measurements for Materials Development in Fusion Research
Available online at www.sciencedirect.com ScienceDirect Energy Procedia 41 (2013 ) 34 39 International workshop on Modification and Analysis of Materials for Future Energy Sources, Energy 2012. 17-20 September
More informationS. Sharafat US ITER TBM Meeting. April 23 24, 2007
Advanced Copper Alloys for FW S. Sharafat US ITER TBM Meeting UCLA April 23 24, 2007 Irradiation Effects on Advanced Copper Alloys Effects of Neutron Irradiation The literatureon neutron irradiation effects
More informationDiffusion phenomenon
Module-5 Diffusion Contents 1) Diffusion mechanisms and steady-state & non-steady-state diffusion 2) Factors that influence diffusion and nonequilibrium transformation & microstructure Diffusion phenomenon
More informationIntegration of Modeling, Theory and Experiments for Fusion Reactor Materials
Integration of Modeling, Theory and Experiments for Fusion Reactor Materials Roger E. Stoller Oak Ridge National Laboratory ReNew: Harnessing Fusion Power Workshop Los Angeles, CA March 2-4, 2009 Role
More informationSTUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS
STUDIES OF TRITIUM BEHAVIOUR IN NEUTRON IRRADIATED BERYLLIUM PEBBLES FOR FUSION APPLICATIONS G. Ķizāne, E. Pajuste, A. Vītiņš, V. Zubkovs Institute of Chemical Physics, University of Latvia, 4 blvd. Kronvalda,
More informationSurface Behavior in Deuterium Permeation through Erbium Oxide Coating
1 FTP/P1-02 Surface Behavior in Deuterium Permeation through Erbium Oxide Coating T. Chikada 1), A. Suzuki 1), C. Adelhelm 2), T. Terai 1), T. Muroga 3) 1) The University of Tokyo, Tokyo, Japan 2) Max-Planck-Institut
More information