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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.
Alireza Haghighat, Ramana Veerasingam
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 237-243
Technical Note | Material | doi.org/10.13182/NT93-A34785
Articles are hosted by Taylor and Francis Online.
Several neutron cross-section libraries used for fluence calculations at the reactor pressure vessel (RPV) based on one-dimensional SN transport calculations are analyzed. It is demonstrated that the BUGLE-80, SAILOR, and ELXSIR libraries yield similar results, while the CASK library predicts significantly different results through and beyond the RPV. The use of the revised ENDF/B- V iron cross sections yields a significant increase in the neutron fluxes beyond the ironcontaining regions. This result has direct impact on the reactor cavity dosimetry that is being considered for the RPV fluence estimation.
