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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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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
Keiichi Saito
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 467-474
Technical Paper | doi.org/10.13182/NSE72-A22514
Articles are hosted by Taylor and Francis Online.
Lehto and Carpenter performed a set of experiments concerning the temperature and the gamma-ray fluctuations in a relatively low power reactor with high fission product inventories. The results are uniformly and quantitatively analyzed by applying the theoretical approach previously developed by the present author. The new features of the present consideration are the following two points: (a) incorporation of the external noise source in the previous theory which includes only the inherent noise source theoretically determined with the use of the first-order linearized Markoffian model of the reactor noise phenomenon; (b) analysis of the cross power spectral density (CPSD) between the two state quantities characterizing the core performances. The first point gives a successful interpretation of most of the experimental results in spite of adopting a simple analytical model. The newly extended framework of the theory can include also a reactivity transfer-function analysis with the use of a proper driving function. The phase of the CPSD between the power and the temperature is calculated on a one-space-point, a one-delayed-group, and a one- or two-feedback-loop reactor model. The results suggest that the experimental determination of the phase will provide both a check point for the theoretical model of the dynamical behaviors of at-power reactors and some bits of information on the feedback parameters.