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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
Jun Liao, Dan Utley
Nuclear Technology | Volume 206 | Number 2 | February 2020 | Pages 191-205
Technical Paper | 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.