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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
X-energy raises $700M in latest funding round
Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
C. A. Bisselle, John A. Wethington, Jr.
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 445-455
Technical Paper and Note | doi.org/10.13182/NT68-A27970
Articles are hosted by Taylor and Francis Online.
A technique was developed for determining the previously unknown thermal-neutron diffusion parameters, ∑a and D, of a small amount of a moderating material, perfluorodimethylcyclohexane, C8F16. A two-region cylindrical system consisting of C8F16 in the core region and water in the reflector region was pulsed with neutrons to obtain the decay constants for several heights of the system. By comparing these results with those obtained from a similar water-graphite experiment and by utilizing one-group, two-region diffusion theory, it was possible to obtain the desired parameters for the fluoro-carbon, i.e., D(C8F16) = 1.02 cm, ∑a(C8F16) = 90 × 10−5/cm, and L(C8F16) = 33.6 cm. This technique offers a convenient method for determining the neutron diffusion parameters of small samples of rare materials.