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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.
Takumi Hayashi, Kazuhiro Kobayashi, Yasunori Iwai, Noriko Asanuma, Shigeru O'hira, Masataka F. Nishi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 647-651
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22667
Articles are hosted by Taylor and Francis Online.
In order to demonstrate tritium confinement performance in DT (deuterium-tritium) fusion reactors at any accident, TPL/JAERI has carried out intentional tritium release experiments using Caisson Assembly for Tritium Safety study (CATS). Some data have been accumulated such as actual tritium behavior in the normal ventilated area and response of tritium monitors and emergency isolation valves. The experimental results of confinement of released tritium of about 3 GBq in 12m3 of the Caisson under ventilation of 50 m3/h were consistent with those of simulation by a three dimensional eddy flow calculation code modified from FLOW-3D. Using this simulation code, the tritium confinement performance in large rooms can be demonstrated for actual fusion reactors.