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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.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Arkadiy A. Yukhimchuk, Vladimyr A. Arkhangel'sky
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 826-830
Design and Model | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22700
Articles are hosted by Taylor and Francis Online.
This paper presents a schematic design of Tritium Fuel Cycle for Muon-Catalyzed Intense Neutron Source (MC INS) capable of producing monochromatic 14 MeV neutrons. Based on the assumption that the fuel mixture should be used in a liquid phase the different approaches are proposed to incorporate a DT cell (synthesizer) into the MC INS facility The estimations of total tritium inventory in ihe MC INS facility are given. The calculations of the DT cell operation temperature regime using the code FLOW 3D are presented. It is shown the capability to remove the thermal energy released in the DT cell of the proposed design. The MC INS design is analyzed from the viewpoint of tritium safety requirements.