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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.
Yi Yuan, M. S. Kazimi, P. Hejzlar
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 135-149
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3888
Articles are hosted by Taylor and Francis Online.
To have adequate confidence in the proposed design of the internally and externally (I&E) cooled annular fuel, it is important to identify the fuel operational constraints from a materials performance perspective. To accomplish this goal, a capability for modeling I&E cooled annular fuel has been developed for two manufacturing approaches: (a) the sintered and pressed pellet approach and (b) the vibrationally compacted (VIPAC) particle approach. New models for the burnup and power radial distribution, fuel thermal and irradiation dimensional changes as well as fuel-cladding interaction mechanisms for annular fuels have been developed and incorporated into a modified version of the FRAPCON code. Fission gas release from the sintered fuel is found to be lower for the same burnup than the traditional solid fuel but slightly higher for the VIPAC fuel. The VIPAC internal rod pressure, however, remains below that of the solid fuel for much higher burnup. The power density constraints and design limits are studied, as well as sensitivity of the annular fuel design to fabrication and operation uncertainties. It is concluded that such fuel can be operated at 30 to 50% higher core power density than the current operating light water reactors, and to a burnup of 80 to 100 MWd/kg U. The major issue for the pellet fuel rod design is the asymmetry in heat transfer that might develop when the outer gap is closed early in the irradiation due to the outward thermal expansion of the fuel. Solutions to this issue via smaller initial inner gap, small roughness and tolerances on fuel and clad surfaces, or the addition of a highly porous ZrO2 layer on the outer pellet surface are evaluated. The main issue for the VIPAC fuel is selection of the particle sizes, which control both the effective density of the fuel and the fission gas release.