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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
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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Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
A. Gandini
Nuclear Science and Engineering | Volume 67 | Number 3 | September 1978 | Pages 347-355
Technical Note | doi.org/10.13182/NSE78-5
Articles are hosted by Taylor and Francis Online.
A critical study of higher order perturbation methods for reactor analysis is made. These methods are classified as explicit, semi-implicit, and implicit, according to their ability to allow perturbative expressions to any order of approximation explicitly in terms of the perturbation. This latter condition is desirable in analytical studies or optimization searches for reactor systems. Emphasis is placed on the problem of real flux normalization. Practical first- and second-order explicit formulations are finally given relevant to perturbations of the flux density. A typical example is described that indicates the potentiality of the so-called “standard method.”