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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.
W. A. Swansiger
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 861-866
Material; Storage and Processing | doi.org/10.13182/FST92-A29857
Articles are hosted by Taylor and Francis Online.
Tritium permeabilities were determined at room temperature, 1.0 MPa (150 psia) tritium for three 23.4 cm diameter EPDM (ethylene-propylene-diene monomer) O-rings using a full-scale mock-up of the AL-SX shipping container seal geometry. The AL-SX container is being developed by Sandia National Laboratories for shipping tritium reservoirs. To determine the tritium permeation rate as a function of temperature, a 50.8 mm diameter EPDM O-ring was tested from room temperature to 150° C at a pressure of 1.0 MPa. Additional permeation measurements were made under the following test conditions: (1) deuterium and helium-4 at room temperature and a pressure of 1.0 MPa using the full-scale AL-SX fixture, (2) tritium from 0.1 MPa to 1.0 MPa at 142° C using the 50.8 mm fixture, and (3) deuterium from room temperature to 150° C at a pressure of 1.0 MPa using the 50.8 mm fixture. Multiple permeation runs using the three full-scale O-rings showed the average room temperature, 1.0 MPa steady state tritium permeation rate to be about 1 × 10−2 Pa-liter/sec (7.6 × 10−5 torr-liter/sec or 1 × 10−4 std cc/sec), well within the allowable limit of 7.1 × 10−2 Pa-liter/sec for tritium release from the AL-SX container. Based on the temperature dependence derived from tests on the 50.8 mm fixture, the permeation rate through the large O-ring at 1.0 MPa tritium, 150° C would be about 60% of the allowable limit. The tritium permeability was found to vary linearly with pressure within the range explored.