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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Charles R. Marotta
Nuclear Science and Engineering | Volume 77 | Number 1 | January 1981 | Pages 107-109
Technical Note | doi.org/10.13182/NSE81-A21343
Articles are hosted by Taylor and Francis Online.
The algebraic difference between the average neutron lifetime (l) and the average generation time (g), referred to as the excess time E (= l − g), is shown to be a useful parameter giving physical insight into the degree of utilization of neutrons toward a chain reacting process in a complicated fissionable system. It can be used to support physical arguments in checking the validity of complex computer results as well as to give some rationale as to what results to expect in these calculations. The concept is applied to the classic criticality case of dry or wet storage of separated fuel assemblies in a variable density hydrogenous moderator.