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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.
Robert C. Ward, Don Steiner
Fusion Science and Technology | Volume 33 | Number 2 | March 1998 | Pages 210-217
Technical Paper | doi.org/10.13182/FST98-A29
Articles are hosted by Taylor and Francis Online.
The impact and status of the cross sections for production of short-lived radioactivities in the intense high-energy neutron fields associated with deuterium-tritium fusion reactors is investigated. The main concern relative to these very radioactive species is that they may represent enhanced radiation sources not accounted for in typical transport calculations. These enhanced radiation sources may affect heat removal and shielding requirements. The status of nuclear data required to assess these issues is surveyed. Among the factors considered in defining the relevant reactions and setting priorities are quantities of the elemental materials in a fusion reactor, isotopic abundances within elemental categories, the decay properties of the induced radioactive by-products, the reaction cross sections, and the nature of the decay radiations. Attention has been focused on radioactive species with half-lives in the range from ~1 s to 15 min. Available cross-section and reaction-product decay information from the literature are compiled and examined. The evaluated data sets are collapsed using neutron spectra from three fusion reactor designs - ARIES I and II and the International Thermonuclear Experimental Reactor (ITER). The group-averaged cross-section sets are then used to produce neutron-spectrum-averaged, one-group cross sections, which are, in turn, used to produce decay heating reaction rates for each of the reactions. The decay heating rate is used as a measure of the radiation source strength associated with a given reaction. The decay heating reaction rates are compared against neutron heating reaction rates. Calculated decay heat to neutron heating ratios are required to be >10% in order for the reaction to be considered of importance for further study. The reactions of importance are identified as 28Si(n,p)28Al, with a ratio of ~10%, and 207Pb(n,n')207mPb, with a ratio >50%. The 28Si(n,p)28Al reaction could affect heat removal requirements for reactors employing silicon carbide as a structural material. The 207Pb(n,n')207mPb reaction could affect heat removal and shielding requirements for shield designs employing lead. Identified reactions of slightly less importance are 27Al(n,p)27Mg, 9Be(n,)6He, 52Cr(n,p)52V, 16O(n,p)16N, and 204Pb(n,2n)203mPb - all of which have ratios between 1 and 4%.