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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.
Om Prakash Joneja, Vijay R. Nargundkar
Fusion Science and Technology | Volume 8 | Number 3 | November 1985 | Pages 2721-2726
Technical Note | Blanket Engineering | doi.org/10.13182/FST85-A24693
Articles are hosted by Taylor and Francis Online.
The multilayered blanket concept introduced initially in spherical geometry has been extended to tokamak geometry, which has been approximated by an annular disk geometry for the present calculations. Tritium production is determined, using such commonly available materials as lead, natural lithium, and graphite/water. The Morse-E general geometry package is employed to simulate the blanket geometry and the plasma region where the neutrons are produced. Calculations are performed for both the block- and the multilayered-type blanket configurations. Using water as a moderator/reflector, the multilayered arrangement gives a 75% higher tritium production compared to the block-type blanket with the same overall size of assembly. The advantage in tritium breeding due to the multilayered arrangement remains practically the same when 10 vol% stainless steel structural material is used; however, the absolute value of tritium breeding decreases by 6 to 8%. Calculations are reported for a homogeneous, block, and multilayered arrangement of materials. Using lead, natural lithium, and water in the annular disk geometry, an overall thickness of 35 cm would be sufficient to give tritium breeding of 1.32/source neutron.