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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
Herve Issard, Pascale Abadie
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 2-8
Special Issue Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems | doi.org/10.13182/NT11-A12538
Articles are hosted by Taylor and Francis Online.
Dry storage cask materials must withstand severe temperature conditions coming from conservative ambient assumptions and from envelope values of residual heat from spent fuels. TN International (TNI) research and development has consequently developed and characterized neutron-shielding materials that show high shielding capabilities and correspond to the needs of a range of temperatures. Aging tests of specimens have been performed accordingly.This paper shows the results of aging tests on shielding material Vyal-B, a material patented by TNI.TNI Vyal-B shielding material is composed of a thermoset resin matrix (vinylester resin in solution of styrene) and two mineral fillers (alumina hydrate and zinc borate). The cross-linking of the polymer leads to a rigid three-dimensional lattice, solid and resistant to transport conditions, especially the temperatures.TNI Vyal-B's shielding ability for neutron radiation is related to the atomic density of hydrogen and boron. Atomic densities can be calculated from the chemical composition and bulk density of samples, and these two parameters are checked initially just after manufacturing.Assessment of the long-term behavior of TNI Vyal-B shielding material has been carried out through exposition tests of samples at different temperatures (150°C to 170°C). The test results give the variations of chemical composition and density. After the aging tests, the new chemical compositions are taken into account in the shielding analysis of the package. Considering a degradation mechanism following Arrhenius behavior, a maximal temperature of long-term use, for example, for interim storage, was confirmed equal to 160°C.