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.
Michael Philip Short, Ronald George Ballinger
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 366-381
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A13481
Articles are hosted by Taylor and Francis Online.
A material system that resists lead-bismuth attack and retains its strength at very high temperatures has been developed that enables increased outlet temperature and the promise of allowing increased coolant velocity and efficiency of lead- and lead-bismuth-cooled reactors if the behavior reported here is confirmed by long-term tests. The development of this system represents an enabling technology for lead-bismuth-cooled reactors. The system is a functionally graded composite (FGC), with separate layers engineered to perform corrosion resistance and structural functions. Alloy F91 was chosen as the structural layer of the composite because of its strength and radiation resistance. An Fe-12Cr-2Si alloy was developed based on previous work in the Fe-Cr-Si system, and was used as the corrosion-resistant cladding layer because of its chemical similarity to F91 and its superior corrosion resistance in lead and lead-bismuth in both oxidizing and reducing environments. The availability of the FGC will have significant impacts on lead-bismuth reactor design. The allowable increases in outlet temperature and coolant velocity lead to a large increase in power density - either to a smaller core for the same power rating or to more power output for the same-size core. In this paper, we report on the overall design of the FGC. We also discuss the general implications for lead-bismuth-cooled reactor design. In a future paper, we will discuss the fabrication and the initial evaluation of the actual product produced using commercial processing methods.