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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Remembering Charles E. Till
Charles E. Till
Charles E. Till, an ANS member since 1963 and Fellow since 1987, passed away on March 22 at the age of 89. He earned bachelor’s and master’s degrees from the University of Saskatchewan and a Ph.D. in nuclear engineering from Imperial College, University of London. Till initially worked for the Civilian Atomic Power Department of the Canadian General Electric Company, where he was the physicist in charge of the startup of the first prototype CANDU reactor in Canada.
Till joined Argonne National Laboratory in 1963 in the Applied Physics Division, where he worked as an experimentalist in the Fast Critical Experiments program. He then moved to additional positions of increasing responsibility, becoming division director in 1973. Under his leadership, the Applied Physics Division established itself as one of the elite reactor physics organizations in the world. Both the experimental (critical experiments and nuclear data measurements) and nuclear analysis methods work were internationally recognized. Till led Argonne’s participation in the International Nuclear Fuel Cycle Evaluation (INFCE), and he was the lead U.S. delegate to INFCE Working Group 5, Fast Breeders.
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 | 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.