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Fusion Science and Technology
Pact signed on potential BWRX-300 deployment in Saskatchewan
Ontario-based GEH SMR Technologies Canada Ltd. and the Saskatchewan Industrial and Mining Suppliers Association (SIMSA) announced yesterday the signing of a memorandum of understanding focused on the potential deployment of the BWRX-300 small modular reactor in Saskatchewan.
The MOU calls for engaging with local suppliers to maximize the role of the Saskatchewan supply chain in the nuclear energy industry.
Nathan C. Reid, Lauren M. Garrison, Chase N. Taylor, Jean Paul Allain
Fusion Science and Technology | Volume 75 | Number 6 | August 2019 | Pages 510-519
Technical Paper | dx.doi.org/10.1080/15361055.2019.1612659
Articles are hosted by Taylor and Francis Online.
In reactor-relevant fusion divertor conditions, tungsten (W) will be used as an armor material due to its excellent thermal properties. It will be exposed to impurities from numerous sources, including ion implantation and mixing, neutron transmutation, low-Z plasma-facing-component (PFC) redeposition and codeposition of deuterium and tritium fuel, and trapped helium bubbles. The impurity plasma material–interaction effects are a concern because they can cause gradual degradation of the material and of plasma performance due to dust formation, fuel retention, and even changes to the thermal and mechanical properties of the W armor. It is crucial to measure the amount of impurities in W, and the glow discharge–optical emission spectroscopy (GD-OES) technique is exceptionally well suited for analysis of irradiated samples. GD-OES can measure a sample’s elemental composition by sputtering the surface of the sample, ionizing the eroded material, and measuring the optical emission of the excited atoms. In order for the GD-OES technique to be applied to neutron-irradiated tungsten samples, a mounting system for miniature samples was designed. The sample mounting and centering procedure was successful in measuring the depth distribution of control W and W alloy sample elemental concentrations. These control depth spectra will be used as elemental references for postirradiated samples. The residence time of surface layers was measured, a comparison of signals from different anodes was completed, and the influence of initial surface roughness or nonuniformity was understood. The depth distribution of an arc-welded W-0.4% rhenium (Re) alloy was measured to have a stable Re signal that was distributed evenly in the W matrix. The methods developed here will allow for quantification of impurities and transmutation amounts in neutron-irradiated W. GD-OES is a powerful tool but requires calibration and careful optimization of the parameters to obtain meaningful results.