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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.
Manfred Bloser, Thomas Beuth
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 114-119
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2823
Articles are hosted by Taylor and Francis Online.
The completion of the direct disposal of spent fuel project and thus the implementation of technical developments in the field of direct disposal are within reach. Politically, these developments are reflected in the 7th amendment of the Atomic Energy Act (the so-called Artikelgesetz), which gives safe disposal of spent-fuel elements the same level of priority as safe reprocessing.Since the 1960s, the Federal Republic of Germany pursued the concept of nonretrievable final disposal of radioactive waste in deep geological formations. The results of the direct disposal project show that there are no substantial changes required for this concept. Within the framework of the project, it was demonstrated that the radiological and mining-related safety objectives of final disposal in a mine can be realized. With the termination of the basic activities in the direct disposal project, specific questions about the feasibility of technical implementation were tackled in a comprehensive manner. However, this does not mean that all issues relating to direct disposal have already been resolved, citing for example the verification of long-term safety based on site-specific data with consideration of geochemical processes and the actual planning of emplacement areas for different types of waste (spent fuel, vitrified high-level waste, medium-activity waste, etc.). One topic area for further research and development relates to questions of gas generation and its control. Increased knowledge of the material behavior of rock salt and of crushed salt - as used for backfilling - is prerequisite for a site-specific assessment of geology and the long-term safety.