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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
R. N. Hwang
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 119-130
Technical Paper | doi.org/10.13182/NSE75-A26651
Articles are hosted by Taylor and Francis Online.
This paper describes some general characteristics of the uncertainties in various fast-reactor parameters as a function of the corresponding uncertainties in nuclear data on the basis of statistical theory. By using the variational formalism, it is possible to relate the mean-square deviation of any reactivity coefficient (or reaction-rate ratio) to the covariance matrix of cross sections. The qualitative behavior of the uncertainties in fast-reactor parameters can be best illustrated geometrically in terms of the region of tolerance. The latter is the volume bound by a “hyper-ellipsoid” surface specified by the designer’s tolerance limit, the coefficients characteristic of the type of parameter in the system under consideration, and the correlation matrix. Exploratory studies and graphical illustrations are given for some cases of practical interest.