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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.
I.N. Sviatoslavsky, G.L. Kulcinski, G.A. Moses, M.E. Sawan, R.L. Engelstad, E. Larsen, E. Lovell, J. MacFarlane, E. Mogahed, R.R. Peterson, J.W. Powers, L.J. Wittenberg
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 634-639
Inertial Fusion | doi.org/10.13182/FST91-A29416
Articles are hosted by Taylor and Francis Online.
SIRIUS-T is a study of an advanced tritium production facility which utilizes direct drive symmetric illumination inertial confinement fusion provided by a KrF laser. Symmetrically illuminated reactor systems have some very unique problems which have to do with a large number of beams. In SIRIUS-T, a single shell ICF target is illuminated by 92 symmetrically distributed beams around a spherical cavity of 4 m radius. The driver energy is 2 MJ and the target gain 50. The first wall consists of graphite tiles bonded to an actively cooled vanadium structure. There is a 1.0 torr xenon buffer gas in the cavity. The structural material is the vanadium alloy V-3Ti-1Si, the breeding/cooling material is lithium 90% enriched in Li-6 and the neutron multiplier is Be, giving a tritium breeding ratio of 1.903. The total tritium inventory in the reactor is 184 g. A routine release of 29 Ci/d is estimated and the maximum accidental release is 19.9 g. At 100 MJ yield, a repetition rate of 10 Hz and an availability of 70%, a tritium surplus of 33.3 kg per calendar year is achieved. Using 100% debt financing, and a 30 full power year (FPY) reactor lifetime, the cost of tritium production is $8,885/g at 5% interest on capital and $14,611/g at 10% in 1990 dollars.