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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
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
Technical Session|Sponsored by MSTD
Wednesday, November 16, 2022|10:00–11:45AM MST|Kaibab
Session Chair:
Annabelle Le Coq
Alternate Chair:
Jake R. Quincey
Session Organizer:
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Effective Thermal Conductivity of UO2-Metal Platelet Composites
10:00–10:20AM MST
JangSoo Oh (KAERI), YongSik Yang (KAERI), JaeYong Kim (KAERI)
Paper
Experimental Investigation of Degradation Mechanisms in ATF Coated Cladding Under Transient Conditions
10:20–10:40AM MST
Hwasung Yeom (Univ. Wisconsin, Madison), Tyler Dabney (Univ. Wisconsin, Madison), David Kamerman (INL), James Corson (U.S. Nuclear Regulatory Commission), Brent Heuser (Univ. Illinois, Urbana-Champaign), Kumar Sridharan (Univ. Wisconsin, Madison)
Neutronics Assessment of Advanced Fuel Claddings in the Equilibrium LWR Core Design
10:40–11:00AM MST
Kingsley Ogujiuba (NCSU), Khang Hoang Nhat Nguyen (NCSU), Yong-Joon Choi (INL), Jason Hou (NCSU)
Neutronic Analysis of Novel Accident Tolerant Control Blade in Boiling Water Reactor (BWR) Core
11:00–11:20AM MST
Arnold Pradhan (Univ. Idaho), Indrajit Charit (Univ. Idaho)
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