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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.
K.G. Porges, M.M. Bretscher
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1903-1908
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29620
Articles are hosted by Taylor and Francis Online.
Measurement of the local breeding rate in a large assembly of fusion blanket candidate materials, irradiated by a fusion neutron source, serves the dual purpose of blanket design support and, perhaps more importantly, of testing analytical methods and cross-section libraries. In this report, we present technical details of a tritium production rate measurement scheme based on the use of neutron irradiation of encapsulated lithium metal samples and subsequent thermal digestion of the samples in a metered carrier hydrogen stream, conversion to THO and LS-counting. A comparison of the scheme to other means of tritium production rate (TPR) measurement with respect to accuracy and other characteristics indicates that its potential accuracy exceeds that of wet-chemistry tritium extraction from lithium salt pellets or TLD deployment and is comparable to the best accuracy of lithium-glass traversing schemes. The sample fabrication and tritium extraction techniques that will be described evolved from well-tested equipment that was previously used in critical (fission) reactor work and cross section measurements, but needed some modification to increase the throughput and thus allow processing the large number of samples required in blanket assay. The applicability of this scheme to measurements at arbitrarily high neutron flux and higher temperatures will be briefly commented on.