ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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
February 2025
Nuclear Technology
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Latest News
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
W. J. FADER, R. C. HARRISON
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 405-414
Technical Paper | doi.org/10.13182/NSE61-A26042
Articles are hosted by Taylor and Francis Online.
Reactor period-reactivity relations and open-loop transfer functions may be determined directly by numerical integration of “rod-drop” neutron decay data without analysis into delayed neutron period and abundance values. Period-reactivity relations obtained by this method for two critical assemblies with and without beryllium in the core and reflector are compared with corresponding results calculated from the “in-hour” equation. Results of the application of the rod-drop experiment to the determination of the open-loop reactor transfer function are given for the beryllium-moderated assembly.