Fundamental Studies of Tritium Diffusivity in Irradiation Defective Lithium Aluminate and Lithium Zirconates Pellets Used in TPBAR
- National Energy Technology Laboratory (NETL), Pittsburgh, PA, Morgantown, WV, and Albany, OR (United States)
Due to its excellent irradiation behavior at elevated temperatures, lithium aluminate (LiAlO2) is used in the form of annular ceramic pellets enriched with the 6Li isotope in tritium producing burnable absorber rod (TPBAR). To simulate the nuclear characteristics and produce tritium (T), TPBAR is irradiated by a neutron flux in a pressurized water reactor (PWR). The T diffuses through the pellets and is captured by the metal getter where it chemically reacts and leads to formation of metal hydride. The transport of T in radiation damaged pellets that contain defects and impurities is not clearly understood due to the lack of fundamental studies of T solubility and diffusivity. The other candidate material possessing a similar physical and chemical properties and can be potentially useful as a tritium breading blanket in the future is Lithium Zirconates (Li2ZrO3). In FY2017, we investigated the diffusion and solubility properties in irradiation defective LiAlO2 and Li2ZrO3 crystals with different level of tritium concentration. In FY2018 we continued to explore the diffusivity and solubility properties extensively in those candidate materials.
- Research Organization:
- National Energy Technology Laboratory (NETL), Pittsburgh, PA, Morgantown, WV, and Albany, OR (United States)
- Sponsoring Organization:
- USDOE Office of Fossil Energy (FE)
- DOE Contract Number:
- FWP- WFO-2816053 Tritium Science - FY18
- OSTI ID:
- 1839416
- Report Number(s):
- DOE/NETL-PUB-22212; TRN: US2302678
- Country of Publication:
- United States
- Language:
- English
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