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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.
Doonyapong Wongsawaeng, Donald Olander
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 279-291
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3876
Articles are hosted by Taylor and Francis Online.
A liquid metal (LM) consisting of one-third weight fraction each of Pb, Sn, and Bi has been investigated as the bonding substance in place of He in the pellet-cladding gap of light water reactor fuel elements. The LM bond eliminates the large T over the preclosure gap that is characteristic of helium-bonded fuel elements. Because the LM does not wet either UO2 or Zircaloy, simply loading fuel pellets into a cladding tube containing LM at atmospheric pressure leaves unfilled regions (voids) in the bond, which lead to local fuel hot spots. Voids were eliminated during fabrication by first evacuating the rod loaded with solid alloy and a fuel stack, melting the alloy, pushing down the fuel stack to drive the LM into the gap, and finally applying at least 5 atm He overpressure. Fabrication of a 4-m-long full-scale fuel rod using this technique was successfully demonstrated. A destructive examination revealed numerous breaks in the frozen alloy bond, but all of these appeared to result from handling the fuel rod. Application to commercial fuel manufacturing should require only minor modifications to existing fabrication lines. The most suitable nondestructive examination technique utilizes a collimated X-ray beam to probe edge-on the region between the pellet surface and the cladding inside diameter.