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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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Nuclear Science and Engineering
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January 2025
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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.
Kohyu Fukunishi
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 215-225
Technical Paper | doi.org/10.13182/NSE77-A26958
Articles are hosted by Taylor and Francis Online.
Multivariate autoregressive (AR) procedures are introduced as diagnostic tools to extract dynamic,characteristics for detection of malfunctions of a boiling water reactor (BWR) power plant. The problem of estimating AR matrices is equivalent to identifying, from measured random signals of a BWR station, the dynamic parameters of a stationary linear discrete time system derived from an unmeasured uncorrelated white-noise process. To explain the characteristics of a derived AR spectra , a general multiple-input, single-output model is discussed. The experiments were carried out in a 460-MW(e) BWR station. The power spectral density of the averaged neutron flux is decomposed into terms corresponding to sources of noise at points of measurement, where the origin of the noise neutron fluctuation is studied. It is shown fom the analysis that a disturbance of high intensity in neutron fluctuation of the BWR is not Caused by the process var Such Core flow but is possibly caused by the inherent noise.specifically defined in this paper, of the neutron flux itself.