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
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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Latest News
WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
G. Dharmadurai
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 345-349
Technical Paper | doi.org/10.13182/NSE83-A15455
Articles are hosted by Taylor and Francis Online.
A simple acoustic mismatch model can predict heat flow across solid/fluid interfaces at high temperatures in terms of known physical properties of the system. Using this model, the thermal boundary conductances of the various interfaces involved in heat transfer from the fuel pellet to the cladding of fast reactor fuel rods are estimated. The typical values of fuel-cladding gap conductance of helium-bonded fast reactor fuel rods quoted in the literature are in reasonable agreement with estimates obtained from this model. In addition to its striking simplicity, an interesting and novel feature of this fundamental approach is the prediction of a marginally high gap conductance for a helium-bonded oxide fuel rod over its carbide counterpart.