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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.
J.R. Stencel, J.D. Gilbert, O.A. Griesbach, J.M. Greco
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 1047-1053
Measurement of Tritium | doi.org/10.13182/FST88-A25276
Articles are hosted by Taylor and Francis Online.
Measurements within the Tokamak Fusion Test Reactor (TFTR) vacuum vessel atmosphere in 1985 indicated low levels of tritium oxide (HTO). From January to July 1987 approximately 3 × 1018 D-D fusion neutrons were produced in TFTR operations. These reactions would be expected to produce a triton for each reaction or 5.4 GBq (145 milliCuries) of tritium. An HTO measurement made of the vessel on 7/10/87, five days after the last pulsing of the machine, but before the machine was let up to air, indicated an HTO level of 1 MBq m−3 (28 µCi m−3) or approximately six times the DOE concentration guide value of 185 kBq m−3 (5 µCi m−3). The ICRP 30 Derived Air Concentration (DAC) limit of 800 kBq m−3 (22 µCi m−3) will become the limit when Draft DOE Order 5480.11 is implemented. A venting program for the vessel was set up with the objective of limiting the internal dose equivalent to personnel working inside the vacuum vessel. An HTO/HT measurement indicated a 57:1 ratio. HTO was detected in Neutral Beam Injectors (NBI). Tritium concentrations were also detected in a roughing pump in oil/water mixtures within the pump reservoirs. The water to oil tritium concentration ratio was 660:1. The graphite indicated an outgassing effect during the activities within the vessel. In addition, the loose powdered graphite with its tritium absorption presented the first known contamination problem for a tokamak operation. Smearable contamination levels up to 600 Bq/100 cm2 (36,000 dpm/100 cm2) were detected inside the vacuum vessel. This paper discusses the measurements, contamination problems, and results of dealing with the first operational health physics tritium-related activity in a fusion energy research tokamak.