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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Luis Alva, Xinyu Huang (Univ of South Carolina), George Jacobsen (General Atomics)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 598-604
The nuclear fuel cladding undergoes severe thermal shock during reflooding of the nuclear core after a loss of coolant accident (LOCA). The purpose of this work is to evaluate the resistance of SiCf-SiCm composite cladding to such thermal shock events. In order to achieve this goal, a nuclear grade SiCf-SiCm composite tube, manufactured by General Atomics (GA), was quenched from an outer surface temperature of 1000 ºC into room temperature (RT) water and hot water. The composite tube was heated by a tungsten rod placed inside the tubular sample to simulate the fuel pellet. The tungsten rod was heated to a centerline temperature of 1400 ºC by an induction coil. To monitor the progressive damage of the SiCf-SiCm composite tube, the acoustic emission (AE) technique is used to acquire the acoustic signals during the test. The samples quenched into RT water showed visible cracks while the sample quenched in hot water did not. Some of the AE signals are related to cracks in the material during quenching. After quenching, the burst strength of the SiCf-SiCm composite tube is measured using a bladder technique. Results show that the SiCf-SiCm composite tube retains more than 88% of its strength after quenching.