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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.
Keitaro Kondo, Isao Murata, Axel Klix, Klaus Seidel, Hartwig Freiesleben
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 591-595
Nuclear Data | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A9274
Articles are hosted by Taylor and Francis Online.
For the International Thermonuclear Experimental Reactor (ITER), the European Union intends to introduce a test blanket module using liquid lithium lead. In the present study, a preliminary experiment was conducted using a LiAl/Pb assembly, which has a neutronics performance similar to lithium lead. The neutron spectrum at the inside of the assembly was measured with an NE-213 detector. We found that the spectra calculated with MCNP5 and JENDL-3.3 underestimate the 14-MeV peak by no less than 30%, while ENDF/B-VII.0 and JEFF-3.1 gave good agreement. The neutron nuclear data of lead stored in JENDL-3.3 may have some problems.
