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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.”
Hiroyuki Ogiwara, Akira Kohyama, Tatsuya Hinoki
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 866-870
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST05-A795
Articles are hosted by Taylor and Francis Online.
Reduced activation ferritic/martensitic steels (RAFs) are leading candidates for blanket and first wall of fusion reactors where effects of displacement damage and helium production are important subjects to be investigated. To obtain systematic and accurate information of microstructural response under fusion environment, dual-ion irradiation method was applied. In order to estimate the microstructural response under fusion neutron irradiation environment, ion-beam irradiation was carried out with helium and metallic self ions. The study is focused on JLF-1 single- and dial-ion irradiated up to 60 dpa at 693, 743 and 793 K. The damage rate and helium injection rate were 1.0 × 10-3 dpa/sec and 15 × 10-3 appm He/sec. At 743 K, void cavity structure was observed under dual-ion irradiation where the contribution of void structure on hardening was not so significant. Irradiation hardening and swelling were depended for the case of dual-ion irradiation. It is attempted to quantitatively relate the dislocation and cavities to the irradiation induced hardening.