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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
Helmut Holzbauer, Lothar Wolf
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 166-181
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2940
Articles are hosted by Taylor and Francis Online.
GOTHIC is an advanced code for thermal-hydraulic flow simulation in nuclear reactor containments and other confinements. Battelle Europe has participated in the development and verification of the code over a number of years.Described are blind and open posttest calculations of the Heiss Dampf Reaktor hydrogen-mixing experiments E11.2 and E11.4 in comparison with measured data.Caused by a miscalibration of steam source flow rates and neglect of the heat sink capability of the instrumentation cooling lines, the pressure, temperature, and steam concentrations were drastically overpredicted by the blind predictions and are quantitatively not comparable to experimental data.The following conclusions can be drawn from the parametric open posttest calculations:1. Scenarios with homogeneous containment atmosphere (like E11.4) can be simulated accurately with lumped-parameter models.2. The lumped-parameter method is seemingly not fully qualified to predict the hydrogen distribution in a stratified containment atmosphere (like E11.2).3. Improved predictive quality may require the application of distributed parameter models.