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6th RaDIATE Collaboration Meeting

Dec 9–13, 2019
TRIUMF
US/Pacific timezone

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Session

4th Oral session

Dec 10, 2019, 9:00 a.m.
TRIUMF

TRIUMF

4004 Wesbrook Mall, Vancouver, BC V6T 2A3 CANADA

Conveners

4th Oral session: Radiation Damage Studies I

  • Slava Kuksenko (United Kingdom Atomic Energy Authority)

Presentation materials

There are no materials yet.

  1. 20. Measurement of displacement cross section in J-PARC for proton kinematic energy range from 0.4 GeV to 30 GeV
    Dr Shin-ichiro Meigo (J-PARC/JAEA)
    2019-12-10, 9:00 a.m.
    Oral presentation
    For damage estimation of structural materials in the accelerator facility, displacement per atom (DPA) is widely employed as an index of the damage calculated based on the displacement cross section obtained with the calculation model. Although the DPA is employed as the standard index of material damage, the experimental data of displacement cross section are scarce for a proton in the energy...
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  2. 18. Fatigue Performance of Proton Irradiated Ti6Al4V Alloy
    Dr Sujit Bidhar (Fermi National Accelerator Lab)
    2019-12-10, 9:25 a.m.
    Oral presentation
    Titanium alloy Ti6Al4V currently used in beam windows in accelerator facilities are subjected to thermal stresses and high cycle fatigue loading due to intense pulsed proton beam. There materials interacting with beam will also undergo various radiation damage which will affect their endurance limit. Till now there is no fatigue data available for high energy proton irradiated titanium alloy....
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  3. 2. Status of Post Irradiation Examinations of the RaDIATE CERN2 capsule
    Mr Nicola Solieri (CERN)
    2019-12-10, 9:50 a.m.
    Oral presentation
    The contribution will provide a status report of the Post Irradiation Examination of the RaDIATE-sponsored CERN2 capsule. The PIE will focus on the Mo-coated samples (MoGR and CfC), including microscopy analysis as well as coating adhesion. Perspectives on the schedule as well as on the other samples will be provided.
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  4. 6. In situ tensile testing and electron backscatter diffraction characterization of irradiated 316L from Spallation Neutron Source Targets 8 and 9
    David McClintock (Oak Ridge National Laboratory)
    2019-12-10, 10:15 a.m.
    Oral presentation
    Tensile testing of material from the Spallation Neutron Source (SNS) Target 2 showed abnormally large ductility for a specimen irradiated to approximately 5.4 displacements per atom (dpa). Subsequent electron backscatter diffraction (EBSD) characterization of these tested Target 2 specimens showed deformation-wave behavior from transformation-induced plasticity was responsible for the large...
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