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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
A. Pazy, G. Rakavy, I. Reiss, J. J. Wagschal, Atara Ya’ari, Y. Yeivin
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 280-295
Technical Paper | doi.org/10.13182/NSE55-280
Articles are hosted by Taylor and Francis Online.
The purpose of this article is an up-to-date, detailed, and rigorous presentation of the generalized least-squares procedure developed by our group to improve neutron cross-section evaluations, based on direct cross-section measurements by means of integral data. Both discrete and continuous (energy dependent) integral quantities are considered. Explicit expressions are derived for the best estimates of the cross sections in a continuous form, as well as in the multigroup approximation. The procedure is illustrated by results relating to the updated Los Alamos data on spherical metallic critical assemblies and the latest ENDF/B cross-section library. It is demonstrated that by minor modifications of the ENDF/B cross sections, most of the experimental data can be reproduced within their quoted uncertainties.
