Development of a robust Be/F82H diffusion bond for ITER TBM R.M. Hunt Fusion Nuclear Science & Technology Annual Meeting August 2, 2010 Introduction Engineering • Application: Development of TBM technologies vital for future fusion demonstration reactors – Breeder blanket structural material Reduced activation ferritic/martensitic (RAFM) steel – Plasma facing armor material Beryllium is one primary candidate • Prospective Joining Process: Hot Isostatic Pressing (HIP) • Scope of Research: – Create methodology for development of a robust diffusion bond between beryllium and RAFM steel – Characterize the strength of the developed bond – Simulate cyclic thermal loading in FEM to determine min. strength criteria • Plastic relaxation of interface from differential thermal expansion • Crack initiation and growth at interface edges Armor coating on plasma facing surfaces 2/12 Background Engineering Important bonding considerations: • Formation of brittle intermetallic layers – – – – • Be is highly reactive w/ most of the elements in the periodic table These often have much less desirable mechanical properties than parent materials Formation is not easily predictable Bond strength appears to be inversely proportional to width of certain reaction layers [1] Excessive heat treatment of the bonded materials – Beryllium shows grain coarsening above roughly 850 °C [2] – Post weld heat treatments for F82H occur at 750 °C [1] • Incomplete coalescence of surfaces if temperature is not sufficiently high Narrow window for bonding conditions Importance of high strength bond: • High heat flux creates stress from differential thermal expansion of dissimilar materials • Cyclic high heat pulses from plasma cause fatigue in joint Method for Achieving Robust Heterogeneous Joints Engineering • Insert diffusion barrier – to prevent formation of deleterious BeCu & BeFe intermetallics – Limited material options. Ti used with good results in ITER FW application – Ti diffuses well into both Be and Cu [4] • Insert compliancy layer (pure Cu) – to reduce stress from differential thermal expansion [5] – And to prevent formation of FeTi [6] • Recent work in Japan [2] and Korea [7,8] on Be//FMS bond – Used Cr/Cu and Ti/Cu layer combinations with promising results Copper Beryllium Titanium Initial Experiments Engineering RAFM Steel • Prior to inclusion of Beryllium – Anneal Ti/Cu coupons • To measure penetration depth of Ti in Cu and Cu in Ti – Fabricate Cu/RAFM HIP coupons • Test strength of Cu/RAFM interface • Determine optimum HIP conditions 5 cm 5/12 Strength of Cu/RAFM interface Tensile behavior of HIPed Cu/F82H Engineering Sample processed at: • 650 ° C – Failed w/o plasticity at 134 MPa – Fractured surface revealed polishing markings • 700 ° C – Failed at UTS of Cu (210 MPa), though still at interface – Surface shows some attachment of Cu • 750, 800, 850 °C – Ductile failure in Cu – Peak strength above strength of parent Cu Fractured surface – HIPed @ 700 C Cross-sec – HIPed @ 850 C F82H F82H Cu Cu 100 μm e 10 μm e Support during Experiment Engineering • Received support from vendors/labs across the country: – F82H donated by JAEA (F82H), Beryllium S65 by Brush-Wellman (Elmore, OH) – Cans machined at UCLA MAE shop – Deposition of thin film at Thin Film Technology (Buellton, CA) – Surface prep at SNL-Livermore (Livermore, CA) – E-beam weld closure of cans at Electrofusion Products (Fremont, CA) – HIP cycles by Bodycote (Andover, MA) – Test specimen EDM cut by Axsys Technologies Inc. (Cullman, AL) – Mechanical tests and AES provided by SNL-Livermore – Toughness tests performed at UCSB Materials Eng. Dept. – SEM + EDS/WDS analysis at UCSD Pisces Lab Fabrication of Full Be/RAFM Joint Engineering • Utilized results from Ti/Cu and Cu/RAFM interfacial studies to narrow conditions • First 4 samples – varied HIP temperature and diffusion barrier thickness – additional rounds to follow Interlayer 1 Interlayer 2 Test No. HIP Temp. Material Thickness Material Thickness #1 700 °C Ti 10 μm Cu 20 μm #2 700 °C Ti 20 μm Cu 20 μm #3 750 °C Ti 10 μm Cu 20 μm #4 750 °C Ti 20 μm Cu 20 μm #5-(10) TBD TBD TBD TBD TBD 8/12 1st Round of Samples Engineering • Samples debonded after attempt to wire cut • No mechanical tests could be performed 9/12 Failure Mechanism Investigation Engineering Auger Electron Spectroscopy (AES) and Energy Dispersive Spectroscopy (EDS) used to characterize compositon Auger #3 & #4 Auger #2 Auger #1 EDS #1 EDS #2 Auger #5 Bond: 700 C, 10µm Ti Bond: 750 C, 20µm Ti 10/12 Backscatter SEM + EDS (performed at UCSD Pisces Lab) Titanium Copper Chromium Iron HIP @ 700 °C -- 10µm Ti + 20µm Cu Engineering Titanium Copper Chromium Iron HIP @ 750 °C -- 20µm Ti + 20µm Cu Current Work Engineering Investigation of cause for debond • High oxygen content in Titanium deposition • Additional EDS/WDS across unfractured samples to see Be/Ti diffusion FEM Work • copper relaxation during thermal stressing • crack initiation and growth at interface 12/12 References 1. 2. 3. 4. 5. 6. 7. 8. Engineering T. Hirose, M. Ando, H. Ogiwara , H. Tanigawa, M. Enoeda, M. Akiba, Fus. Eng. Design, doi: 10.1016/j.fusengdes.2010.06.002. D.W. White Jr. and J.E. Burke, The Metal Beryllium, The American Society for Metals, 1955. ITER. ITER Structural Design Criteria for In-vessel Components. G 74 MA 8 01-05-28 W0.2. P. Sherlock, A. Erskine, P. Lorenzetto, A.T. Peacock, Fus. Eng. Design, 66 (2003) 425. N. Baluc, DS Gelles, S. Jitsukawa, A. Kimura, RL Klueh, GR Odette, B. Van der Schaaf, and J. Yu. Status of reduced activation ferritic/martensitic steel development. Journal of Nuclear Materials, 367:33{ 41, 2007. 61 S. Kundu, M. Ghosh, A. Laik, K. Bhanumurthy, GB Kale, and S. Chatterjee. Diffusion bonding of commercially pure titanium to 304 stainless steel using copper interlayer. Materials Science & Engineering A, 407(1-2):154{160, 2005. J.S. Lee, J.Y. Park, B.K. Choi, D.W. Lee, B.G. Hong, and Y.H. Jeong. Beryllium/ferritic martensitic steel joining for the fabrication of the ITER test blanket module rst wall. Fusion Engineering and Design, 84(7-11):1170{1173, 2009. Jeong-Yong Park, Yang-Il Jung, Byung-Kwon Choi, and Yong-Hwan Jeong. Current status of R&D in fabrication technology of plasma facing components for ITER rst wall and TBM. Korea Atomic Energy Research Institute, September 2009.