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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.
Craig Brown, Ken Hartley, Jim Hulsman
Nuclear Technology | Volume 151 | Number 2 | August 2005 | Pages 120-125
Technical Paper | Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization | doi.org/10.13182/NT05-1
Articles are hosted by Taylor and Francis Online.
Boiling water reactors (BWRs) in the United States have transitioned over the past 30 yr from 7 × 7 and 8 × 8 fuels, 12-month cycles, and batch average burnups of 30 GWd/tonne U to 10 × 10 fuel, 18- to 24-month cycles, batch average burnups of 50 GWd/tonne U, and 5% power uprates in the 1990s. The next step for BWRs in the new millennium is 24-month cycles and extended power uprates as high as 120% power. These operating conditions lead to large reload fuel batch sizes (up to 45% of the core) that result in lower batch average discharge burnups (~45 GWd/tonne U). Parameters driving the drop in fuel burnup include enrichment limitations and the need for fuel performance improvements. The next steps to achieve better BWR fuel cycle economics and their associated benefits and implementation challenges are discussed in this paper.
