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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.
Yu-Huai Shih, Shih-Jen Wang, Kai-Cheng Chuang, Tzu-En Huang
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 340-352
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-145
Articles are hosted by Taylor and Francis Online.
The Fukushima Daiichi accident occurred on March 11, 2011. A seismic event and tsunami induced an extended station blackout plus loss of the ultimate heat sink. Three units progressed into a core melt severe accident. The accident occurred in the emergency operation procedure (EOP) domain. However, this situation was already beyond the scope of an EOP. The operator followed the EOP faithfully, and a core melt situation still occurred. An interesting topic is whether it is possible to avoid this type of accident. The purpose of this study is to survey the Fukushima accident progression with respect to the effect of the containment venting strategy for the Chinshan Nuclear Power Plant EOPs. Under the emergency situation, only a small reactor pressure vessel (RPV) injection system was available. This type of accident may be avoided by an early shift from the EOP to the severe accident guideline (SAG), switching from high-pressure injection to low-pressure injection while the reactor core isolation cooling system is available, gradually lowering the RPV pressure, and maximizing the injection flow rate. The plant responses and accident physical phenomena were simulated using MAAP5. The results show that the consequences of an uncovered core and core melt can be avoided by adopting the proper RPV depressurization and containment venting strategy.