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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
2020 ANS Virtual Winter Meeting
November 15–19, 2020
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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.
Yu Weng, Fangfang Cao, Xiaobing Tuo, Hongfang Gu, Haijun Wang
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 93-104
Technical Paper | dx.doi.org/10.1080/00295639.2017.1417345
Articles are hosted by Taylor and Francis Online.
In a 1250-MW pressurized water reactor (PWR), coolant is injected into the reactor vessel under accident conditions through the method of direct injection, which is the most important function of the emergency core cooling system. Since the problem has been found that safety injection start-up will have a significant thermal effect on the reactor’s internal system, a confirmatory study of an improved structure is required in the initial design stage. In this paper, the heat transfer and flow characteristics of the core barrel, the neutron shielding panels, and the radiation surveillance capsules are investigated by a scaled experiment combined with a numerical method to obtain the distribution of the wall temperature and the convective heat transfer coefficient on the outer wall of the reactor internals under different injection conditions. In addition, potentially dangerous parts have been pointed out, and dimensionless correlations are fitted to describe the heat transfer laws of key parts of reactor internals for use in reactor design. This research fills in the gaps in the study of heat transfer under direct injection of the reactor internals in a PWR, providing support for the safety of the reactor structure.