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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
A. Nava Dominguez, Y. F. Rao
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 173-193
Technical Paper | doi.org/10.1080/00295450.2018.1442085
Articles are hosted by Taylor and Francis Online.
The Canadian Nuclear Laboratories (CNL) is developing the technologies to enable the use of thorium-based fuels in pressure tube–heavy water reactors (PT-HWRs). One of the key stages in developing the thorium-based fuels for PT-HWRs is the reactor core configuration. Currently at CNL there are 20 core configurations under investigation, which involve several types of thorium-based fuels that could be implemented in a 700-MW(electric)-class PT-HWR. Among these core configurations, four fuel bundle concepts are being considered: (1) the reference (or nominal) 37-element bundle; (2) a 37-element modified bundle, with the center element using a different fuel material; (3) a 35-element bundle; and (4) an 18-element internally cooled annular fuel bundle. This study presents the steady-state subchannel thermal-hydraulic assessment of the 20 core configurations under investigation. The hottest channel approach is used in this study, as it represents the upper limit of a feasible design. The axial and element power distributions used in the analysis correspond to those of the discharge burnup. Three mass flows are considered in this study: 13.5, 21, and 24 kg/s. Five parameters are used to evaluate the fuel channel/bundle performance, namely, minimum critical heat flux ratio, channel pressure drop, enthalpy distribution, void fraction, and core power.