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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Warren F. Witzig, Ross T. Thomas
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 251-263
Technical Paper | doi.org/10.13182/NSE79-A20615
Articles are hosted by Taylor and Francis Online.
Multidimensional linear regression analysis is employed as a modeling technique for the prediction of boiling water reactor (BWR) shutdown margin reactivity. A comparison is made between the best models developed using regression analysis and the General Electric (GE) three-dimensional BWR core simulator code. The GE code is based on one-group diffusion theory, and its accuracy is verified by comparison with experimental data. One use of this code is the calculation of shutdown margin throughout a fuel cycle, but it requires a large computing facility not located at a reactor site. The regression models give an approximation of a core's shutdown margin based on current core physics parameters. The method can be utilized at a BWR plant site to provide information demonstrating compliance with license and technical specification requirements. The results obtained by regression predictions for the two cores studied compare favorably with current industry methods. After establishing a regression model, predictions can be made at a reactor site using a pocket calculator.