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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NWMO chooses vendors for Canadian repository
Canada’s Nuclear Waste Management Organization has selected five companies it is to work with to design and plan the organization’s proposed deep geologic repository for spent nuclear fuel. As the owner of the project, the NWMO will be working with WSP Canada, Peter Kiewit Sons (Kiewit), Hatch Ltd., Thyssen Mining Construction of Canada, and Kinectrics.
Technical Session|Sponsored by THD
Wednesday, June 16, 2021|12:00–1:45PM EDT
Session Chair:
Robert P. Martin
Alternate Chair:
Dillon R. Shaver
Session Organizer:
Matthew D. Zimmer
Staff Producer:
Jessie Vazquez (ANS)
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Thermal Decomposition of Carbonates as a Passive Cooling Mechanism for Molten Salt Reactors
Christopher Forsyth (Univ. of California, Berkeley)
Paper
Study of Sodium Pool Fire Model Improvement in MELCOR for SFR
David L.Y. Louie (Sandia National Laboratories), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)
Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR
Robert F. Kile (Univ. of Tennessee Knoxville), Friederike Bostelmann (ORNL), Steve E. Skutnik (ORNL), William A. Wieselquist (ORNL), Nicholas R. Brown (Univ. of Tennessee Knoxville)
Modeling of HTTF test PG-26 using RELAP5-3D and SAM
Aaron Epiney (INL), Thanh Hua (ANL), James Wolf (INL), Ling Zou (ANL), Gerhard Strydom (INL), Rui Hu (ANL)
Safety Assessment of Composite Alternative Moderators for Modular High Temperature Gas-Cooled Reactors
Veronica Karriem (Univ. of Tennessee Knoxville), Edward M. Duchnowski (Univ. of Tennessee Knoxville), Nicholas R. Brown (Univ. of Tennessee Knoxville)
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