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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.
Hae Yong Jeong, Hee Cheon No
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 52-64
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2908
Articles are hosted by Taylor and Francis Online.
A few features of the reflood model in RELAP5/MOD3.1 have been modified to improve the unrealistic prediction results of the model. In the new method, the modified Zuber pool boiling critical heat flux correlation is adopted in the range of mass flux G < 150 kg/m2s. The new criterion for reflood drop size, which is characterized by the use of We = 1.5 and a minimum drop size of 0.0007 m for p* 0.025, has been suggested based on some experimental data and the correlation derived through regression analyses of many reflood experiments. To describe the wall-to-vapor heat transfer at low pressure and low flow, the Webb-Chen correlation is utilized. The suggested method has been verified through simulations of the Lehigh University rod bundle reflood tests. A sensitivity study shows that the effect of drag coefficients is dominant in the reflood model. It is proved that current modifications result in much improved quench behavior and accurate wall and vapor temperature predictions when they are compared with those by the frozen version of RELAP5/MOD3.1.