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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.
Zaphar-Ullah Koreshi, Asaf Kinrot, Jeffery D. Lewins
Fusion Science and Technology | Volume 22 | Number 3 | November 1992 | Pages 371-387
Technical Paper | Blanket Engineering | doi.org/10.13182/FST92-A30096
Articles are hosted by Taylor and Francis Online.
The TIBER II blanket design is chosen for a neutronic sensitivity analysis using Monte Carlo perturbation theory. A preliminary analysis is carried out with both deterministic and Monte Carlo simulation codes to estimate the sensitivity of the tritium breeding in the blanket to the atomic density ratio of tungsten multiplier and aqueous solution breeder. Derivatives of the neutron collision density in the blanket are then sampled using the collision estimator in the MORSE code. It is found that for small perturbations, the neutron fluxes and tritium breeding rates can be predicted quite accurately, thus saving substantial computing in a preliminary design study.