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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.
Yuan Chen, Gang Chen, Rong Liu, Haiping Guo, Wenjiang Chen, Wenmian Jiang, Jian Shen
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1919-1924
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-A29622
Articles are hosted by Taylor and Francis Online.
Using the Total Absorption Method, the neutron multiplications in beryllium have been measured. A deionized water sphere with outer radius of 75 cm and a polyethylene sphere with outer radius of 69 cm were used as the total neutron absorbers. Neutron distributions in the spheres were measured using 235U fission chambers. The relative and the efficiency-determined methods were compared. Important sources of experimental errors were detailly analyzed. 4 groups of neutron multiplications in beryllium up to 14.85 cm thick for two total absorbers and two methods of measurement have been obtained and agreement among them is satisfactory. Measured results have been compared with ANISN calculations using data from ENDF/B-IV. It is shown that the differences between calculations and experiments are up to 15%.
