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2020 ANS Virtual Winter Meeting
November 16–19, 2020
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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Jun Liao, Dan Utley
Nuclear Technology | Volume 206 | Number 2 | February 2020 | Pages 191-205
Technical Paper | dx.doi.org/10.1080/00295450.2019.1599614
Articles are hosted by Taylor and Francis Online.
Westinghouse Electric Company (Westinghouse) is developing its next generation of high-capacity nuclear power plants (NPPs) based on lead fast reactor (LFR) technology: a Generation IV compact, highly simplified, passively safe, and scalable NPP. In addition to superior economics for enabling competitiveness even in the most challenging electricity market, exceptional safety performance is actively pursued in the design of the plant, leveraging the inherent favorable properties of lead coolant as well as safety features intrinsic in the design. Being that decay heat removal (DHR) is an integral part of any NPP’s safety philosophy, a systematic process of concept selection has been employed across a wide variety of DHR system designs. Among them, air cooling outside of the reactor vessel (RV) is one of the concepts that has been actively evaluated by Westinghouse. In this paper, the use of air cooling in nuclear reactors is discussed together with the identification of benefits and challenges associated with RV air cooling in LFR technology. The heat removal capability of this system is assessed with three computer codes, differing in complexity and suitability to “rapid prototyping” design activities carried out by Westinghouse during different phases of plant design. Though the computer codes were developed separately, the results of the three evaluation models tend to support each other, thus increasing confidence in the information provided to progress the Westinghouse LFR design and establish its safety basis. Additional validation through existing and potentially new test data is foreseen as future work within the Westinghouse LFR program.