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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
J. H. Kim, I. K. Park, B. T. Min, S. W. Hong, S. H. Hong, J. H. Song, H. D. Kim
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 378-395
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3849
Articles are hosted by Taylor and Francis Online.
Triggered steam explosion experiments have been carried out in the TROI facilities to investigate the energetics of the steam explosions. Two types of corium melt were used as a melt. One was eutectic corium at 70:30 wt% (UO2:ZrO2), and the other was corium at 80:20 wt%. The diameter of the water pool was 0.6 m, and the depth was varied from 0.67 to 1.3 m. An external trigger (PETN, 1.0 g) was applied just before contact of the melt and the bottom of the interaction vessel, which is believed to be the time of a possible spontaneous triggering. The external trigger led to triggered steam explosions in all the experiments. In the experiments with 70:30 corium, the maximum recorded dynamic pressure and the dynamic load were 17.0 MPa and 360 kN, respectively. Meanwhile, in the experiment with 80:20 corium, the maximum dynamic pressure and the dynamic load reached 7.7 MPa and 200 kN, respectively. The energetics obtained from the triggered steam explosion tests with 70:30 corium were greater than those from the triggered experiment with 80:20 corium. The strength of a triggered steam explosion was found to depend on the composition of the corium.