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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.
Truong V. Vo, Timothy M. Mitts, Tyrone R. Blackburn, Hanh K. Phan
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 179-193
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35248
Articles are hosted by Taylor and Francis Online.
A risk assessment of potential events at Susquehanna Steam Electric Station (SSES) is described wherein a loss of cooling occurs in a spent-fuel pool (SFP). This evaluation was performed as part of the evaluation of potential generic issue 93-01, regarding the safety impact of incidents involving the loss of SFP cooling (SFPC). The analysis investigates allegations and concerns identified in a Title 10, Part 21 Code of Federal Regulations (10 CFR 21) report filed by two former contract employees, who alleged that SSES has design deficiencies associated with SFPC that make it susceptible to unsafe conditions. The evaluation estimates the likelihood of a loss-of-SFPC event at SSES and the associated probability of the SFP heating up to nearboiling conditions. The evaluation also includes an assessment for such near-boiling events for their contribution to core damage and an estimate of order-of-magnitude core damage frequency. The analysis addresses SSES plant conditions that existed prior to the 10 CFR 21 report and also current plant conditions. Data for this analysis were obtained from the SSES licensee and from other relevant data sources, including probabilistic risk assessment information. Background for the evaluations performed, the methodology used in the evaluation, the data and modeling used for the analyses, the analysis techniques and results, and conclusions are presented.