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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
M. Moscardini, S. Pupeschi, Y. Gan, F. A. Hernández, M. Kamlah
Fusion Science and Technology | Volume 75 | Number 4 | May 2019 | Pages 283-298
Technical Paper | doi.org/10.1080/15361055.2019.1565481
Articles are hosted by Taylor and Francis Online.
In this work, an in-house thermal–Discrete Element Method (DEM) code, recently developed at Karlsruhe Institute of Technology to evaluate the heat transfer in ceramic packed pebble beds, was applied to study the thermal behavior of the breeder beds of the European solid breeder blanket concept. The breeder zone of the helium-cooled pebble bed (HCPB) blanket for the Demonstration (DEMO) reactor was considered as the reference model implementing the same materials, applying the related neutronic heating, and simulating the relevant bed thicknesses. The code was used to evaluate the temperature profile generated by the neutronic heating in the thickness of the breeder bed. A column cutout of packed pebbles bounded by upper and bottom walls, representing the cooling plates of the HCPB, was considered as a representative geometry to carry out the work. The implemented three-dimensional network model evaluates the heat transfer inside packed beds through chains of thermal resistances describing the thermal contacts (particle-particle and particle-wall) occurring in the assembly. Besides thermal transport through the mechanical contact area, thermal transport through the surrounding gas phase is accounted for including the Smoluchowski effect. Sensitivity studies revealed the influence of the operational conditions and the parameters that mainly affect the temperature profile in the bed.