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.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
Chlng-Kong Chao, Che-Chung Tseng
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 202-211
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34781
Articles are hosted by Taylor and Francis Online.
A loading-rate-dependent model has been developed for the analysis of pellet/cladding mechanical interaction that takes the power ramp rate into account. Based on knowledge of the local strain rate behavior, the effect of ramp rate on fuel rod performance is well described by using the strain energy density criterion. The threshold value of the strain energy density for fuel cladding is determined from the Studsvik Inter-Ramp Project experimental data in conjunction with stress analysis. The critical strain energy density for recrystallized Zircaloy-2 is found to be 0.32 MPa. With this value, the damage zone of cladding for a specific fuel rod design under various burnups, ramp rates, and ramped terminal linear heat generation rates can be established, and the ramp rate effect is well identified.
