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.
R. G. Alsmiller, Jr., J. Barish
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 318-321
Technical Note | Material | doi.org/10.13182/NT77-A31794
Articles are hosted by Taylor and Francis Online.
Calculated results are presented of the variation with position in the experimental volume of a Li(D,n) neutron radiation damage facility of the damage energy and helium and hydrogen production in copper and in niobium when this volume is partially filled with experimental samples. At a given position in the experimental volume for either copper or niobium, the ratio of the damaged energy with no absorber to the damaged energy with a 50-mm-thick iron absorber or a 100-mm-thick carbon absorber is never >3 and in most positions is <2. The neutron nonelastic cross-section data at the higher energies (>15 to 20 MeV) needed to carry out the transport calculations were obtained from the intranuclear-cascade model of nuclear reactions.