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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.
George D. Cremeans
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 745-754
Technical Paper | TMI-2: Decontamination and Waste Management / Radioactive Waste Management | doi.org/10.13182/NT89-A27667
Articles are hosted by Taylor and Francis Online.
The March 1979 accident at Three Mile Island Unit 2 and the subsequent 10-yr cleanup generated ∼8706 m3 (∼2300000 gal) of radioactively contaminated water, herein referred to as accident-generated water (AGW). Although most, if not all, of this inventory could be decontaminated to acceptable regulatory levels governing river discharge and released to the Susquehanna River, a settlement agreement with the city of Lancaster specifically prohibited the utility from doing so prior to an acceptable environmental evaluation by the U.S. Nuclear Regulatory Commission. To dispose of this large water inventory, nine alternative disposal methods were evaluated. This evaluation considered each method’s technical feasibility, environmental effect, cost, and public acceptance. On the basis of these criteria, as well as political and institutional considerations, disposal of the AGW by forced evaporation and collection of the evaporated solids was selected as the most acceptable method. The selected method is designed to provide a decontamination factor of 1000 to the radioactive particulates in the AGW. The system consists of (a) a vapor recompression distillation unit to distill the AGW in a closed cycle process and collect the purified distillate for subsequent release by vaporization, (b) an auxiliary evaporatory to further concentrate the bottoms from the main evaporator, (c) a flash vaporizer unit to flash the purified distillate to the atmosphere in a controlled and monitored manner, (d) a blender/dryer to produce a dry solid from the concentrated waste, and (e) a packaging system to prepare and package the solid waste in containers acceptable for shipment and burial at a commercial low-level radioactive waste disposal site. The projected time span for AGW disposal operations is ∼2 yr, allowing for scheduled availability of the 8706-m3 (2300000-gal) inventory and planned system maintenance time. The estimated volume of waste generated, packaged, and shipped during this operation is ∼145 tonnes (∼160 t). The waste conforms to the burial requirements for class A and transportation requirements for low specific activity radioactive material.
