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.
Morris E. Battat, L. A. Ronald Dierckx,+, C. Robert Emigh
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 338-348
Technical Paper | Material | doi.org/10.13182/NT79-A19222
Articles are hosted by Taylor and Francis Online.
A detailed analysis is made showing the feasibility of producing a neutron spectrum that will closely match the first wall neutron environment of any proposed future fusion reactor. An intense neutron source based on the deuterium-tritium reaction and producing 1 to 3 × 1015 14-MeV neutrons per second in a small volume, <1 cm3, is used as the primary source. The spectrum is tailored by surrounding this source with a spherical blanket composed of concentric shells of lithium, uranium (93% 235U), and beryllium. The irradiation volume of ∼100 cm3 is located between the source and the inside of the blanket and can be used for the purpose of radiation damage evaluations.