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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
2020 ANS Virtual Winter Meeting
November 15–19, 2020
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Fusion Science and Technology
UWC 2020: A call for transformational change
Bowing to current COVID-19 realities but buoyed by the success of June’s virtual Annual Meeting, ANS event planners returned to the virtual realm for this year’s Utility Working Conference. Originally scheduled for August 9–12 at Marco Island, Fla., the condensed event was held Wednesday, August 11, wherever registrants’ computer devices happened to be located.
In addition to 26 educational sessions and workshops, UWC 2020 featured an opening plenary session titled “Achieving Transformational Change: A leadership discussion,” moderated by Bob Coward, MPR Associates principal officer and ANS past president (2017–2018). Plenary panelists included representatives from three utilities—Arizona Public Service (APS), Exelon, and Xcel Energy—plus the Institute of Nuclear Power Operations (INPO) and the Nuclear Regulatory Commission.
Takuya Nagasaka, Haiying Fu, Nobuyuki Kometani, Takeshi Miyazawa, Takeo Muroga, Hideo Watanabe, Masanori Yamazaki, Takeshi Toyama
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 645-651
Technical Paper | dx.doi.org/10.1080/15361055.2017.1352428
Articles are hosted by Taylor and Francis Online.
In order to investigate the effect of post-weld heat treatment (PWHT) and post-irradiation annealing (PIA), electron-beam-weld specimens of the reference low activation vanadium alloy, NIFS-HEAT-2, were neutron-irradiated to a fluence of 7.62 × 1023 neutron m−2 (E > 1 MeV) at 563 K in Belgian Reactor-2. In the present experiments, unexpected oxidation of the surface of the samples occurred during the neutron irradiation, and significantly degraded impact properties of the weld metal, while the degradation was not significant for the base metal. The removal of the oxidized layer by electro-polishing improved the impact properties of the weld metal. Although complete removal of the oxidized layer could not be confirmed, it is revealed that impact absorbed energy of the weld metal with post-weld heat treatment at 1073 K was comparable to that of the base metal after the post-irradiation polishing. In other words, irradiation embrittlement of the weld metal was successfully suppressed by the PWHT. PIA at 773 K and above was effective to recover the irradiation hardening and irradiation embrittlement. Mechanisms of the irradiation hardening, irradiation embrittlement and its recovery were discussed.