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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.
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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
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.
Douglas C. Hunt
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 138-165
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31613
Articles are hosted by Taylor and Francis Online.
The methods commonly used in this country to evaluate the criticality safety of fissile material arrays include density analog , surface density, equilateral hyperbola, albedo, and solid-angle techniques. These can be divided into array unit interaction and semiempirical methods. The albedo and solid-angle techniques fall into the former class; the rest fall into the latter class. A study reveals that interaction methods are useful in treating arrays of arbitrary mesh patterns (e.g., triangular or hexagonal) having only a few units, while the semiempirical techniques are more applicable to arrays with a large number of units. The density analog and surface density approaches are easy to apply but typically require more auxiliary calculations, while other methods are more difficult to use, but more broadly applicable. None of the methods satisfactorily handle nonuniformly spaced arrays, arrays with arbitrary amounts of internal moderator, or “clumped” arrays, i.e., arrays of arrays. Most of the methods have some provision for treating mixed arrays, but these provisions often do not apply to arrays of arbitrarily arranged fast (e.g., metal) and slow (e.g., solution) units.