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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
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.
Yoshihiko Kaneko, Shuzi Ohkubo, Fujiyoshi Akino
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 173-176
Technical Note | doi.org/10.13182/NSE73-A23243
Articles are hosted by Taylor and Francis Online.
An improved data processing method is developed for pulsed-neutron measurements in a multiplying medium. The characteristic feature of the method is to determine the value of the prompt-neutron decay constant a as accurately as possible by removing the delayed-neutron decay component from the raw experimental data. The delay ed-neutron decay component is estimated to be the deviation of the response of a one-point reactor from a single exponential decay for repeated pulsed-neutron bursts. It is obtained by taking account of the first and second post-neutron bursts. From the application of the method to some test data provided by calculation and to experimental data from pulsedneutron experiments in the Semi-Homogeneous Ex-periment it is found that the usual data processing method, disregarding the slowly decaying delayedneutron mode, should underestimate the value of a by ∼4% in a near-critical multiplying medium having a neutron lifetime of ∼1 msec.