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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.
Mohamed E. Sawan
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 766-770
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9002
Articles are hosted by Taylor and Francis Online.
Data for 40 of the 71 isotopes/elements in FENDL-2.1 were taken from ENDF/B-VI.8. Following the release of ENDF/B-VII.0 we performed a preliminary assessment for changes made in data of these 40 isotopes/elements. We compared the relevant cross sections in the two libraries. In addition, we carried out MCNP calculations for a calculational benchmark representative of an early ITER design that was utilized during the FENDL development process. In addition, we performed 3-D calculations for an inertial fusion power plant conceptual design. It is concluded that modifying FENDL-2.1 to include the most recent ENDF/B-VII.0 is not urgently needed for ITER analysis. On the other hand, the larger changes in calculated ICF target neutronics parameters and tritium breeding ratio confirm the need for updating FENDL-2.1 for use in analysis of fusion systems beyond ITER. Additional calculations are in progress for integral experimental benchmarks to fully understand the impact of data changes introduced in ENDF/B-VII.0.
