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SC Nuclear Summit focuses on V.C. Summer
The second annual South Carolina Nuclear Summit held last week featured utility executives and legislators from the state, as well as leaders from Brookfield Asset Management, which is being considered to restart construction on the two abandoned reactors at the V.C. Summer nuclear power plant in Fairfield County. The summit, at the University of South Carolina’s Colonial Life Arena, attracted more than 350 attendees. The event was hosted by the university’s Molinaroli College of Engineering and Computing.
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.