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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
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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Nuclear Science and Engineering
June 2024
Nuclear Technology
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Latest News
Waste Management 2024: The symposia at 50
This year marked the 50th anniversary of Waste Management Symposia’s Waste Management Conference, held March 10–14 in Phoenix, Ariz. The event has grown significantly since the first Waste Management Conference in 1974, which attracted about 200 attendees. This year’s conference saw a record attendance of around 3,300 people from more than 20 different countries and boasted 235 technical sessions and 89 exhibitors.
Technical Session|Special Topics
Tuesday, August 22, 2023|3:30–5:10PM EDT|Gunston East/West
Session Chair:
Emre Tatli (Westinghouse Electric Co.)
Alternate Chair:
Graham Macpherson (FNC)
Session Organizer:
Jun Liao
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CFD Modelling of Lead Solidification and Natural Convection for the Westinghouse Lead-Cooled Fast Reactor
3:30–3:50PM EDT
D. Wilson (Univ. Manchester), H. Iacovides (Univ. Manchester), E. Tatli (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), S.J. Lee (Fauske & Assoc.)
Paper
CFD and STH Thermal-Hydraulic Analyses in Support of the CIRCE-THETIS Experimental Campaign
3:50–4:10PM EDT
P. Stefanini (Univ. Pisa), A. Pucciarelli (Univ. Pisa), N. Forgione (Univ. Pisa), I. Di Piazza (ENEA Brasimone R.C.)
CFD Analysis of the Passive Heat Removal System in the Conceptual Design Phase of the Westinghouse Lead-Cooled Fast Reactor Under Air Cooling Conditions
4:10–4:30PM EDT
Aidan Wimshurst (Frazer-Nash Consultancy), Graham Macpherson (Frazer-Nash Consultancy), Rhodri Watkins (Frazer-Nash Consultancy), Carolyn Howlett (Frazer-Nash Consultancy), Jun Liao (Westinghouse Electric Co.), Emre Tatli (Westinghouse Electric Co.), Cory Stansbury (Westinghouse Electric Co.), Megan Durse (Westinghouse Electric Co.), Richard Wright (Westinghouse Electric Co.), Marco Caramello (Ansaldo Nucleare)
Thermal-Hydraulic Analysis of a Representative Westinghouse Lead-Cooled Fast Reactor Fuel Bundle Using CFD
4:30–4:50PM EDT
D. Wilson (Univ. Manchester), H. Iacovides (Univ. Manchester), E. Tatli (Westinghouse Electric Co.), C. Stansbury (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.)
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