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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
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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
November 2022
Nuclear Technology
December 2022
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Latest News
Route readiness elements in a large-scale spent nuclear fuel transportation system
The scale and duration of a national campaign to transport spent nuclear fuel (SNF) from commercial nuclear power plants around the United States would be unprecedented. A meticulous level of planning that considers many elements is needed to inspire public confidence and support.
Technical Session|Sponsored by RPD
Monday, June 14, 2021|1:00–2:45PM EDT
Session Chair:
Pavel V. Tsvetkov (TAMU)
Session Organizer:
Alternate Chair:
Dimitrios Cokinos (BNL)
Staff Producer:
Janice Lindegard (ANS)
This is a standing RPD session with papers on all general reactor physics topics of contemporary interest.
To access the session recording, you must be logged in and registered for the meeting.
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To access paper attachments, you must be logged in and registered for the meeting.
Liquid-fueled Molten Salt Reactor Depletion Modeling
Benjamin R. Betzler (ORNL)
Summary
Area Method Physical Interpretation, Modelling, and Intrinsic Bias
A. Talamo (ANL), Y. Gohar (ANL)
Development and Test of a Novel Neutronic Verification Scheme for Molten Salt Reactors
C. Demazière (Chalmers Univ. of Technology), A. Mylonakis (Chalmers Univ. of Technology), P. Vinai (Chalmers Univ. of Technology)
Studies on Enhanced Spatial Control with Low Enriched Uranium in Plate-Type Fuels
Hailey M. Green (ORNL), Benjamin R. Betzler (ORNL), Andrew T. Nelson (ORNL)
Examination of the Reactivity Limitations and Burnable Poison Loading Requirements for the OPEN100 Core Concept
Andrew Hummel (Kennesaw State Univ.), Joshua Tolbert (Energy Impact Center), Michael Beckert (Energy Impact Center)
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