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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.
Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 18-27
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14516
Articles are hosted by Taylor and Francis Online.
The use of highly-enriched fuels is an effective method for reducing the number of spent fuel assemblies and improving fuel cycle economics, e.g., with >5 wt% 235U. However, from a criticality safety point of view, such high enrichment levels require a significant investment for the considerable modification of most facilities and equipment. Erbia-credit super-high-burnup fuel offers an effective solution that can solve the problem: Small amounts of erbia added to the entire amount of UO2 powder can reduce the reactivity level to less than that observed at a 5 wt% enrichment level, thus eliminating the need for the modifications mentioned above. A series of criticality safety analyses has been performed to determine the minimum and sufficient content of erbia that can guarantee a suitable erbia credit. As a noteworthy result, the erbia content required was determined for corresponding values of uranium enrichment in a range >5 wt%, as indicated in our ECOS (Erbia COntent for Sub-criticality judgment) diagram. This paper outlines a series of criticality safety analyses and explains how the minimum erbia content can be determined to ensure subcriticality for a >5 wt% enrichment fuel to ensure that the fuel obtained is equivalent to that whose enrichment is <5 wt%.