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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Kazuya Furuichi, Kazunari Katayama, Hiroyuki Date, Toshiharu Takeishi, Satoshi Fukada
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 458-464
Technical Note | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-969
Articles are hosted by Taylor and Francis Online.
In this study, tritiated water was poured in a packed bed of natural soil and subsequently distilled water was poured in the bed to recover tritium retained in the soil at room temperature. From tritium balance, 22.5 % (7.1 MBq) of input tritium (31.5 MBq) was retained in the soil bed. By distilled water purge, 70 % (5 MBq) of retained tritium was recovered but 30% (2.1MBq) was left. To recover residual tritium, the soil was immersed in distilled water for 531 days but the amount of tritium released to distilled water was slight (0.04 MBq). A part of the soil immersed in the water was taken out and heated up to 300°C under humid oxygen atmosphere. Tritium release terminated at about 50 hours. 11 % (0.23 MBq) of retained tritium was released. By heating to 1000°C, the release amount of tritium increased proportionally to the time and additional 4% (0.09 MBq) was released at 5 hours. The desorption rates of tritium in each process was quantified.
Tritium is quite slowly released from the natural soil exposed to tritiated water in water at room temperature. However, a long time heating by 1000°C would be required to try to recover all tritium from the contaminated soil positively, although tritium recovery was not completed in this work.