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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.”
Kyu In Shin, Jae Sung Yoon, Dong Won Lee, Suk-Kwon Kim, Jin Hyung Gon, Eo Hwak Lee, Seungyon Cho
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 200-207
Technical Paper | doi.org/10.13182/FST13-752
Articles are hosted by Taylor and Francis Online.
Korea has developed a helium-cooled ceramic reflector (HCCR) test blanket module (TBM) for ITER, and Korean reduced activation ferritic martensitic (RAFM) steel, which is named ARAA (advanced reduced activation alloy), has also been developed for a structural material of the KO HCCR TBM. To evaluate the welding fabrication technology in the TBM, one case of TIG welding conditions was selected based on the previous work by Yoon et al. (2013), and a single pass with one side weld procedure through a thickness in TIG weld was carried out using ARAA, Batch 2 (F206). The microstructure was observed in the base, heat affected zone (HAZ), and weld region, and the micro-hardness was measured from the base to the weld region. In addition, a small punch (SP) test considering the base metal and HAZ region was carried out at room and high (550°C) temperatures. The empirical mechanical properties of the HAZ were estimated based on the correlation between the tensile and SP test in the base metal, and the fracture morphology was observed after the SP test.