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Fusion Tungsten Materials US & JP Collaboration Matrices 2016

A collaborative study between the US and Japan on Tungsten materials for fusion research. The experiment aims to investigate various scientific ideas related to tungsten properties under irradiation, retention, and thermal effects for future PFC development. The RB19J experiment is crucial for understanding the fate of tungsten in plasma-facing components. Detailed specimen preparation, irradiation scope, and facility functions are outlined.

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Fusion Tungsten Materials US & JP Collaboration Matrices 2016

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  1. Fusion Tungsten MaterialsUS & JP Collaboration Matrices2016 W. Geringer, Y. Katoh, L. Garrison, T. Koyanagi

  2. Content • PHENIX Program • RB19J W materials (US & JP) • RB19J capsule design, assembly &irradiation • Rabbit Irradiations • Tungsten radioactivity • TITAN Program • W materials • Completed and planned PIE

  3. Purpose RB19J Experiment • An essential experiment for tungsten research on PFC (identified as the most critical mission for PHENIX) • Outcome will have a large impact on fate of tungsten and future direction of PFC development • Experiment is shared with blanket structural materials research under the QST (previously JAEA) Fusion collaboration program

  4. Material for RB19J L. Garrison, M. Fukuda and all PHENIX colleagues

  5. Summary of US Materials for RB19J Scientific idea to investigate Standard commercial tungsten Versus ITER grade tungsten

  6. Summary of US Materials for RB19J Scientific idea to investigate Anisotropy of material

  7. Summary of US Materials for RB19J Scientific idea to investigate Comparison with previously irradiated SCW in unshielded capsule

  8. Summary of US Materials for RB19J Scientific idea to investigate Effect of tungsten microstructure and impurities on properties

  9. Summary of US Materials for RB19J Scientific idea to investigate Effect of particle inclusion on properties

  10. Summary of US Materials for RB19J Scientific idea to investigate Isolate effects of Re and irradiation damage with model alloys of W-xRe

  11. Summary of JP Materials for RB19J Scientific idea to investigate Thickness dependence on retention (i.e. long time TPE exposure), Thickness dependence on gas-driven permeation

  12. Summary of JP Materials for RB19J Scientific idea to investigate Thermal diffusivity effects Retention study Obtain stress strain data Study heat loading effects with PAL and electron beam

  13. Summary of JP Materials for RB19J Scientific idea to investigate • Observe interfacial microstructure and shear fractures • Investigate pseudo-ductile fracture behavior effects

  14. Summary of JP Materials for RB19J Scientific idea to investigate Measure TD and compare surface roughness effects

  15. Final Specimen RB19J Matrix for PHENIX (W) 6SQ5D Disc SSJ2 NT2

  16. PHENIX RB19J Capsule J. McDuffee, W. Geringer, C. Petrie, R. Howard, N. Cetiner, F. Riley, M. Fukuda, T. Hwang, S. Kondo, C. Bryan

  17. RB19J Neutron Irradiation Scope • Location: Removable Beryllium (RB) • Dose: • W: 1~1.5 dpa, 6 cycles (subject to schedule and change above 1 dpa) • F82H: 2.5~3 dpa, 6 cycles • Temperature regions • 300°C,142 specimens (QST) • 500°C, 406 specimens (PHENIX) • 800°C, 389 specimens (PHENIX) • 1200°C, 359 specimens (PHENIX) • Specimens types incl TD discs, tensile bars, toughness, torsion, tungsten fibres • Gadolinium thermal neutron shield

  18. RB19J Capsule Design Layout Graphite holder: 359 specimens Graphite holder: 389 specimens 500C 1200C Graphite holder: 406 specimens 3xAluminum holders: 142 specimens 800C 300C Total number of specimens = 1296

  19. Thermal Neutron Shield reduces thermal flux to specimens by an order of magnitude • Shield design • Gd sheet • Interlocking plates inside the coolant channel • 1.4 mm thick • 3 cycles in FY16 + 3 cycles in FY17 • Reduces impact on any one FY RB-19J End of 6 cycles Irradiation start Thermal flux reduction due to Gd shield Specimen Region Gd shield

  20. Final Design Layout – Graphite Holders

  21. Final Design Layout – Aluminum Holders

  22. Thermal Design Results 500C 1200C 800C 300C 3xAluminum holders

  23. Specimen Preparation Inspection Specimen machining & preparation Delivery ? Pre-cracking N/A to W Side grooves Irradiation Stacking & assembly Cleaning Sorting

  24. Internal Components – Al Holders ROUNDBAR SSJ3 M3-PCCVN 0.16 CT

  25. Internal Components – Graphite Holders

  26. Capsule Assembly– External Parts Welding and leak testing are performed prior to capsule assembly Gd shield & Al sleeve Holder test fit

  27. Complete RB19J Assembly Internal assembly is enclosed by the Gd shield and Al sleeve and then inserted into the tall outer housing connected to the flexible hose that protects thermal couple wires.

  28. Materials Irradiation Facility (MIF) The MIF is essentially the control room for instrumented experiments. A substantial amount of resources were dedicated to upgrading the MIF to be fully operational. Primary Functions • Serves as a control room for instrumented materials irradiation experiments in the reactor • Provides inert gas (He, Ne, Ar) for experiments • Controls pressure and flow rate • Monitors temperature, pressure and the effluent stream during irradiation

  29. Installation of the RB19J MIF connection RB 19J successfully installed in HFIR on June 6th 2016

  30. First Irradiation – Cycle 466 First irradiation cycle 466 Startup June 14th 2016 • Stabilized zone temperatures on average: • 500 zone: 504°C to 530°C • 800 zone: 802°C to 805°C • 1200 zone: low on average at 1085°C to 1110°C • 300 zone: high on average at 343°C to 374°C.

  31. PHENIX Rabbits T. Koyanagi, M. Fukuda

  32. Status and history of the rabbit irradiation Irradiation started on 01/13/15  and ended on 02/06/15. The rabbits are stored in the HFIR pool.

  33. Specimen matrix Task 2 Task 3 SiC temperature monitor • Same specimen matrix in each of 2 rabbits; • One rabbit operates @ 800C and the other @ 1100C.

  34. Expected radioactivity of W specimens (calculated by M. Fukuda @ Tohoku U.) D10T1 ~1.5g D6T1 ~ 0.6g SSJ2 ~0.45g TEM <0.1g

  35. TITAN – Previous Irradiations L. Garrison, C. Taylor, M. Shimada

  36. 440 Tungsten Samples Were Irradiated in HFIR for the TITAN program • Single crystal tungsten • Wrought tungsten foil • Annealed tungsten foil • Tungsten-Copper laminate This is one of more than 20 rabbit capsules that were part of this irradiation campaign 16 mm

  37. Legend: C=completed P=planned TEM APT PAS T=tensile H=hardness FS=fracture surface SiC=silicon carbide temperature monitors C TEM APT T-broken H SiC C TEM T H SiC T9C-24 P PAS H P TEM T H SiC C none P T H SiC TB-650-1 P H C none TB-650-2 TB-500-1 C T H SiC P none TB-500-3 T9C-5 P TEM PAS H FS C T SiC TB-650-4 TB-650-3 T9C-14 T9C-15 C none P TEM APT-3rd T H SiC TB-500-2 C none P T H SiC C none P T H SiC C TEM T H SiC P TEM-gauge PAS FS C APT T H SiC P TEM PAS FS TB-300-2 T9G-11 C TEM T H SiC P H P none C TEM T H SiC TB-300-3 TB-300-1 TB-300-4 T9G-13 C T H SiC P none P APT-2nd PAS C T H SiC P TEM APT-2nd T H SiC P TEM APT-2nd T H SiC C none C none C none P TEM APT-1st T H SiC PC2A PC3A PC4A PC1A PC5 C none P TEM APT-1st T H FS SiC C TEM PAS T H SiC C TEM PAS T H SiC P none P none C TEM SiC P APT-1st T H L. Garrison, ORNL

  38. Legend: C=completed P=planned TEM APT PAS B=bend H=hardness FS=fracture surface SiC=silicon carbide temperature monitors PIL=piece in LAMDA P TEM B-1st H FS T9C-24 P TEM B-1st H FS SiC C PIL none P TEM H SiC P H C SiC C SiC C PIL none TB-500-1 TB-500-3 TB-500-2 TB-650-1 T9C-5 P H C SiC TB-650-2 TB-650-4 P TEM B-1st H FS C SiC TB-650-3 T9C-15 C SiC C none P H SiC P H T9C-14 C PIL TEM -OW P TEM H SiC C SiC P H P TEM H SiC C PIL TEM -OW TB-300-2 T9G-11 TB-300-3 TB-300-1 P B-2nd H FS C SiC TB-300-4 T9G-13 P B-2nd H FS C SiC P H C SiC C SiC P H C PIL none P TEM H SiC C none P H SiC PC2A PC3A PC4A PC1A PC5 C H SiC P none C TEM H SiC P B-3rd FS P H SiC C SiC P H C none C TEM P B-3rd H FS SiC L. Garrison, ORNL

  39. TITAN samples at INL • 12 broken tensile neutron irradiated SCW samples were shipped to INL FY15. • 2 x irradiation conditions (400 °C, 675 °C, 700 °C). • 3 samples will be tested for the PHX mid term review in FY16. • Positron annihilation • TPE exposure • Identical fluence • Varying temperature • Thermal desorption spectroscopy (TDS) • The other 3 samples will be used for Tritium Plasma Experiments and Nuclear Reaction Analysis studies (FY17/18). 0.1 dpa C. Taylor, PHENIX SCM 2016

  40. Summary • Scientificideas for the W materials inside the RB19J capsule & 2 PHX rabbits: • Comparison studies with previous irradiated non-shielded W • Retention and permeation comparisons • Study thermal diffusivity and heat loading effects • Observe interfacial microstructure and shear fractures • Investigate pseudo-ductile fracture behavior effects • Study effects of microstructure, impurities on properties & material anisotropy • The RB19J is an instrumented experiment that allows for real time monitoring and control. • Gd thermal shielding is to better simulate the fusion flux applicable for W material. • Less material transmutation due to less thermal flux • Lower sample radioactivity • RB19J is planned to complete irradiation in FY17. Shipping and disassembly activity estimated to be ~6 months  Cooling time of specimens for PIE in LAMDA • Large database (1300+ specimens) of various W alloys @ different temperatures & fluences. • Extensive matrix from previous irradiations as well as current irradiations allows for concurrent or overlapping experiments.

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