Evaluation of Pb-17Li compatibility of ODS Fe-12Cr-5Al alloys

JOURNAL OF NUCLEAR MATERIALS

卷:479

Article

Unocic, Kinga A.¹  Hoelzer, David T.¹ 

[1] Oak Ridge Natl Lab, Mat Sci & Technol Div, Oak Ridge, TN 37831 USA

关键词: Pb-7Li compatibility;    Cast FeCrAl;    ODS FeCrAl;    Mass change;    Oxide scale;    LiAlO2;   

DOI  :  10.1016/j.jnucmat.2016.07.017

来源: Elsevier

【 摘 要 】

The Dual Coolant Lead Lithium (DCLL: eutectic Pb-7Li and He) blanket concept requires improved Pb-17Li compatibility with ferritic steels in order to demonstrate acceptable performance in fusion reactors. As an initial step, static Pb-17at.%Li (Pb-17Li) capsule experiments were conducted on new oxide dispersion strengthened (ODS) FeCrAl alloys ((1) Y2O3 (125Y), (2) Y2O3 + ZrO2 (125YZ), (3) Y2O3 + HfO2 (125YH), and (4) Y2O3 + TiO2 (125YT)) produced at ORNL via mechanical alloying (MA). Tests were conducted in static Pb-17Li for 1000 h at 700 degrees C. Alloys showed promising compatibility with Pb-17Li with small mass change after testing for 125YZ, 125YH and 125YT, while the 125Y alloy experienced the highest mass loss associated with some oxide spallation and subsequent alloy dissolution. X-ray diffraction methods identified the surface reaction product as LiAlO2 on all four alloys. A small decrease (similar to 1 at.%) in Al content beneath the oxide scale was observed in all four ODS alloys, which extended 60 mm beneath the oxide/metal interface. This indicates improvements in alloy dissolution by decreasing the amount of Al loss from the alloy. Scales formed on 125YZ, 125YH and 125YT were examined via scanning transmission electron microscopy (S/TEM) and revealed incorporation of Zr-, Hf-, and Ti-rich precipitates within the LiAlO2 product, respectively. This indicates an inward scale growth mechanism. Future work in flowing Pb-17Li is needed to further evaluate the effectiveness of this strategy in a test blanket module. Published by Elsevier B. V.

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