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.
W. F. Murphy, H. E. Strohm
Nuclear Technology | Volume 4 | Number 4 | April 1968 | Pages 222-229
Technical Paper and Note | doi.org/10.13182/NT68-A26320
Articles are hosted by Taylor and Francis Online.
Segments of Type-304L stainless-steel cladding from irradiated EBR-II fuel elements have been used for burst tests from room temperature to 1000°C. The cladding had accumulated exposures of (0.5 to 1.4) × 1022 n/cm2 (> 0.1 MeV) at temperatures between 370 and 500°C. In burst tests at ≤ 700°C, the greater strength was on the lower half of the irradiated cladding where the irradiation temperature was < 475°C. Tests at 800, 900, and 1000°C each showed uniform strength along the lengths of the cladding. The strength of the irradiated specimens decreased most rapidly with temperatures between 400 and 700°C. Unirradiated specimens were weaker than irradiated ones below 700°C; above 700°C, the unirradiated specimens were slightly stronger. The irradiated and the unirradiated specimens had low uniform strain (∼1 and ∼10%, respectively) at temperature of ∼ 400 to 500°C.