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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
WEST claims latest plasma confinement record
The French magnetic confinement fusion tokamak known as WEST maintained a plasma in February for more than 22 minutes—1,337 seconds, to be precise—and “smashed” the previous record plasma duration for a tokamak with a 25 percent improvement, according to the CEA, which operates the machine. The previous 1,006-second record was set by China’s EAST just a few weeks prior. Records are made to be broken, but this rapid progress illustrates a collective, global increase in plasma confinement expertise, aided by tungsten in key components.
P. C. Hall, R. B. Duffey
Nuclear Science and Engineering | Volume 58 | Number 1 | September 1975 | Pages 1-20
Technical Paper | doi.org/10.13182/NSE75-A26763
Articles are hosted by Taylor and Francis Online.
In postulated loss-of-coolant accidents in water-cooled reactors, it is possible for an increase in Zircaloy clad temperature, coupled with reactor depressurization, to give significant local clad strain, and hence reduced area for coolant flow. This paper establishes a simple method of calculating the effect of consequent impairment of local heat-removal capability. An existing flow model, due to Gambill, has been used to estimate the local reduction in the heat transfer coefficient due to clad ballooning. By formulating an energy balance for the fuel pins, temperature transient curves for the distorted cladding are derived from those for undistorted fuel.To analyze the complicated two-phase phenomena, several simplifying assumptions are contained in the flow model. Results, therefore, are given for a range of flow and blockage assumptions, and are shown to be in reasonable accord with an analysis using large and complex computer codes and with all available experimental data.The model can be applied to all types of water-cooled reactors, including pressure tube reactors, by a suitable evaluation of the resistance to bypass flow.