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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.
Yasushi Seki, Isao Aoki, Shuzo Ueda, Satoshi Nishio, Ryoichi Kurihara, Takashi Tabara
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 353-357
Fusion Economics and Reactor Studies | doi.org/10.13182/FST98-A11963639
Articles are hosted by Taylor and Francis Online.
The radwaste generated from three fusion power reactors using ferritic steel, V-alloy and SiC/SiC composite were classified into low level waste (LLW) which can be disposed by shallow land burial (SLB) and medium level waste (MLW) which cannot be disposed by SLB because one or more of the radionuclides exceeds the derived limiting concentration value. When the recently developed FENDL/A2.0 library is used, the SLB fraction became 91% for ferritic steel, 36% for V-alloy and 65% for SiC/SiC. It is found that if the Nb impurity content in V-. alloy and N impurity content in SiC/SiC could be reduced to 1/100 (0.15 Wt.ppm) and 1/20 (5times10−4 Wt.%), respectively, the SLB fraction becomes nearly 100% for both materials. On the other hand, the alloying element W content needs to be reduced to further increase the SLB fraction in case of the ferritic steel F82H.
