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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!
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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.
Sergey Smolentsev, Tyler Rhodes, Yuchen Jiang, Peter Huang, Charles Kessel
Fusion Science and Technology | Volume 77 | Number 7 | November 2021 | Pages 745-760
Technical Paper | doi.org/10.1080/15361055.2021.1906134
Articles are hosted by Taylor and Francis Online.
At present, the U.S. Fusion Engineering Systems Study (FESS) considers several cooling/breeding concepts that utilize flowing liquid metals (LMs), Li, or eutectic PbLi alloy as working fluids for implementation of these concepts in the Fusion Nuclear Science Facility (FNSF). In this paper, we review recent modeling activities aimed at the investigation of LM flows and heat transfer relevant to the FESS-FNSF program. In particular, considerations are given to (1) development and validation & verification of computational magnetohydrodynamic (MHD) codes, (2) characterization of critical coupled MHD/heat transfer phenomena, and (3) design and analysis for selected LM applications in the FNSF. Under these three research thrusts, the reviewed topics including the MHD code HyPerComp Incompressible MHD solver for Arbitrary Geometries (HIMAG), MHD mixed-convection flows, MHD pressure drop in the blanket inlet/outlet manifolds, PbLi flows in a thermal convection loop, MHD PbLi flows in a dual-coolant lead-lithium blanket prototype, and a design window for a flowing Li divertor with He-cooled substrate.