ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
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.