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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Latest News
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.
Guillaume Martin (CEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 113-117
Scenarios of the evolution of the French nuclear fleet are developed by CEA, EDF, ORANO and FRAMATOME, following conservative assumptions in terms of technology, safety, regulation and costs. In the next decades, the SFR demonstrator ASTRID paves the way to the deployment of a few fast reactors used to consume PWR MOX spent fuel in priority. In the 2090 to 2120 period, the number of SFR goes on growing. The fleet eventually comes to a mix of breeder SFR and EPR (European Pressurized water Reactor) supplied with LEU and MOX fuels. Such a fleet composition enables the stabilization of spent fuel and plutonium inventories. Previously, a steady-state regime was reached in the next century, thanks to a fleet composed of ~40% SFR.
A new methodology has been applied. This methodology was recently developed to put into equations the equilibrium conditions of nuclear power systems composed of various reactor types. Fleets with the less SFR are now favored, since SFR are reputed to be more expensive than thermal reactors. Results show that the fraction of SFR in the fleet can be reduced of around 10% in comparison to the fleet previously deployed. However, the fleet composition which minimizes the SFR fraction at equilibrium leads to plutonium contents in EPR MOX fuels near the safety limit which is currently accounted for.