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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.
Kentaro Ochiai, Yury Velzilov, Takeo Nishitani, Paola Batistoni, Klaus Seidel
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 378-381
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A947
Articles are hosted by Taylor and Francis Online.
Tritium benchmark experiments with D-T neutron are a key issue to verify the tritium production rate (TPR) of the fusion blanket. The most useful method to measure the TPR in the neutron benchmark experiments is the liquid scintillation counting with Li2CO3 pellet. Ten years ago, the method of Li2CO3 pellet has been sufficiently verified the accuracy by means of D-T fast neutron irradiation and it was concluded within 10%. However, on the recent breeding blanket design, tritium is dominantly produced with the thermal neutron made with the scattering of D-T neutron and also the accuracy of the tritium production rate is requested below 10%. Therefore, previous verification is not sufficient for the recent blanket design and it is necessary to carry out the activity of the verification again. The JAERI, ENEA and TUD began to carry out the tritium benchmark experiment to verify the tritium production rate for the recent fusion blanket.
