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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.
H. Guo, T. Kooyman, P. Sciora, L. Buiron
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1447-1459
Technical Paper | doi.org/10.1080/00295450.2019.1611304
Articles are hosted by Taylor and Francis Online.
The reduction of the initial excess reactivity in fast reactor cores will enhance the inherent safety level of the cores as it does reduce the impact of control rod withdrawal (CRW) accidents. Compensation for burnup reactivity loss by means of burnable poison (BP) is considered as a possible solution to limit initial excess reactivity. Minor actinides (MAs) challenge long-term nuclear waste management, and they can be transmuted from absorber isotopes to fissile isotopes, which allows them to play the role of BPs.
Two loading modes of MAs as BPs are considered in this paper: The so-called homogeneous transmutation mode mixes MAs with the fuel, and the so-called hybrid transmutation mode packs MAs in independent pins in the fuel assemblies. The content of americium or neptunium in these two modes is considered with regard to current technological feasibility, including burnup, cladding stress, decay heat, and the neutron source of the assemblies considered here. Both of these modes are able to compensate for the reactivity loss of a 3600-MW(thermal) fast reactor and thus reduce excess reactivity at the beginning of cycle.
The impact of MA loading on the core characteristics, including power distribution, material balance, and feedback coefficient, is considered from the assembly level to the core level. The hybrid mode shows better management feasibility while the use of neptunium exhibits a lower impact on the current fuel recycling. Finally, the core behavior during a CRW transient is evaluated, which shows that the core loaded with BPs exhibits better safety performance in CRW transients due to their lower initial excess reactivity.