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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.
Alex Galperin, Gilad Raizes
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 125-132
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35319
Articles are hosted by Taylor and Francis Online.
The possibility exists of utilizing pressurized water reactor (PWR) power plants of current technology for efficient and cost-competitive incineration of excess plutonium. Several plutonium-based fuel cycle options were considered, i.e., pure 239Pu or reactor-grade plutonium as a fissile component and natural uranium or thorium as a fertile component of the fuel. A typical PWR was chosen as the base for detailed analysis and comparison of all investigated fuel cycle options. A series of calculations was carried out for each of the fuel cycle options generating “equilibrium” cycles of equal length. Results of the design analysis and comparison of main performance parameters were used to compare different fuel options. Material mass balances were calculated to evaluate the plutonium incineration potential of the considered options. A potential of efficient reduction of excess plutonium was demonstrated for all considered fuel options. The thorium-based fuel cycles were found especially effective for destruction of fissile isotopes of plutonium (>1000 kg/yr). This was partially compensated by the buildup of 233U isotope. One of the important conclusions of this work is that significant amounts of fissile plutonium may be incinerated in thorium-based cycles and that 233U may be denatured by addition of modest amounts of natural uranium. Preliminary economic evaluations indicate that plutonium incineration may be carried out in existing PWRs without economic penalty and may, therefore, present a viable alternative to other plutonium disposition methods.