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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
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
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Robert J. Teitel, John B. Brown
Nuclear Technology | Volume 1 | Number 1 | February 1965 | Pages 13-24
Technical Paper | doi.org/10.13182/NT65-A20459
Articles are hosted by Taylor and Francis Online.
The Liquid Metal Breeder (LIMB) reactor is an internally-cooled fluid fuel reactor based upon a Th232-U233 thermal breeder cycle. It employs a molten lead coolant, a uranium-bismuth solution fuel, a thorium bismuthide dispersion in lead-bismuth blanket fluid and a graphite moderator. Heat from the fuel is transferred through a graphite fuel element to the coolant which transports the heat to an external boiler and pump. This arrangement overcomes the major disadvantages found in previous “externally-cooled” liquid-metal-fuel reactors. Equilibrium concentrations of uranium isotopes heavier than U233 and other reasonable assumptions were derived from existing information and then used to develop a broad survey of LIMB reactor sizes. Two sizes, 200 and 1000 MW(th), were chosen for more detailed evaluation. The 200 MW(th) has a potential breeding ratio of 1.08 and an 8 year doubling time. The 1000 MW(th) reactor has a breeding ratio of 1.05 and a 12 year doubling time. Using the most pessimistic estimates on processing could reduce the breeding ratio, while improvements in design and the utilization of low-cross-section coolants can counteract these losses. LIMB reactor technology can lead to an efficient breeder, even in large power sources, and warrants further engineering evaluations.