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
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
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.
B. W. Lee, S. H. Levine
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 130-136
Technical Paper | doi.org/10.13182/NSE77-A26944
Articles are hosted by Taylor and Francis Online.
The increase in intensity of a 252Cf neutron source surrounded by uranium depleted in the 235U isotope has been measured, and the results of this experiment were used to determine of238U for 252Cf spontaneous-fission neutrons. The measurement was performed in the TRIGA Mark III reactor, using the multiplication property of a subcritical TRIGA core. A Monte Carlo calculation was performed, which employed ENDF/B-III data, to provide analytical results for comparison with the measurements. The source enhancement obtained using a depleted uranium cylinder surrounding the 252Cf source was measured to be (7.35 ± 0.20)% compared with a calculated value of (7.11 ± 0.15)%. The calculated results, using ENDF/B-III data, agree with the measurement within the uncertainty of the evaluated values of v and σƒ.
