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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.
Ralph W. Moir
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 1169-1177
Fusion Power Reactor, Economic, and Alternate Concept | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40312
Articles are hosted by Taylor and Francis Online.
If the present research program is successful, heavy-ion beams can be used to ignite targets and to produce high gain for yields of about 350 MJ. HYLIFE-II is a power plant design based on surrounding such targets with thick liquid (Flibe, Li2BeF4) so that the chamber and other apparatus can not only stand up to these 350 MJ bursts of energy but do so without replacing components during the plant's 30-year life. The capacity factor will be increased and the cost of component replacement will be decreased. Continuous improvements to the design are being made to increase safety, decrease the generation of radioactive material, and reduce the cost of electricity (COE). Improvements discussed in this paper decreased COE for each effect by the amount in parentheses: increased plant size (22%), increased capacity factor and reduced component replacement (20%), reduced remote maintenance equipment (3.2%), use of non-nuclear grade chamber, pumps and piping (2.9%), reduced tritium inventory by a factor of 2.4, reduced excess tritium production with attendant increase energy release in the blanket (1.8%), corrected treatment of Flibe inventory costs (3.4%).