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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.
T. Vollmer, U. Besserer, K. Borcherding, J. Dehne, H. Dilger, L. Dörr, M. Glugla, W. Hellriegel, E. Hutter, R. Kraemer, R.-D.Penzhorn, B. Reinhardt, D. Röhrig, K. Schubert
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 988-994
Tritium Safety | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30534
Articles are hosted by Taylor and Francis Online.
The Tritium Laboratory Karlsruhe (TLK) is a facility of the Forschungszentrum Karlsruhe GmbH (FZK) where, under the European Fusion Technology Program, experiments are performed on tritium technology for the nuclear fuel cycle with a view to the needs of the ITER fusion reactor. The Laboratory comprises conventional infrastructure systems, tritium infrastructure systems, and experiments on a floor area of approx. 1200 m2. The licensed tritium quantity is at present 20 g; an application to increase this amount has been submitted to the corresponding authorities. The measures taken to safely handle such amounts of tritium are described in detail in this paper. Whereas the infrastructure is operated and controled from a central process control system (PLS), for the experiments local control systems (LLS) are used. Safety relevant signals are linked to a safety circuit. Some safety signals relevant to the operation of tritium systems are connected to the Central Emergency Control Center of the Research Center. Besides the operating, control and monitoring measures the safe operation of the Tritium Laboratory relies on highest quality standards, clear plant operation rules, a high degree of inherent safety and a number of tritium monitoring systems according to the latest state of the art.