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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.
Wade Marcum, Daniel LaBrier, Emory Brown, Yikuan Yan, Nicolas Woolstenhulme
Nuclear Technology | Volume 206 | Number 6 | June 2020 | Pages 895-910
Technical Paper | dx.doi.org/10.1080/00295450.2020.1720559
Articles are hosted by Taylor and Francis Online.
In 2017 the Transient Reactor Test (TREAT) Facility was restarted after having been placed in a standby state in 1994. The TREAT reactor’s restart has since enabled the progressive development of new nuclear technologies within the United States that previously were outsourced to other countries. While the reactor’s restart was a large feat worthy of recognition, the experimental use of its characteristics has required further development of an in-pile experimental infrastructure sufficient to support programmatic needs. This hardware has taken the form of capsule designs (compact and elongated) as well as loop concepts representing the phenomena of interest for a subset of the separate effects tests desired for each respective testing campaign. The transient testing program has been a large integrated effort that aligns with the U.S. Department of Energy’s current needs. This study complements those programmatic elements by developing, fabricating, and demonstrating a full-scale flowing water loop in an out-of-pile environment. The goal of this effort is to develop a pragmatic understanding of the engineering capabilities and limitations associated with geometric form factors, metering technology, and controls logic under the representative thermal-hydraulic conditions that would be experienced within the TREAT reactor during an in-pile reactivity-initiated accident test. The outcomes of this study result in an evaluation of the conceptual design of a comprehensive flowing water loop, including objective figures of merit for comparing unique instrumentation and the basis for their selection during operations. These efforts directly contribute to and are required for the further advancement of transient testing capabilities within the United States.