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
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
M. J. Ades, K. L. Peddicord, S. D. Montgomery
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 47-58
Technical Note | doi.org/10.13182/NSE83-A17456
Articles are hosted by Taylor and Francis Online.
A promising fuel concept for fast breeder reactor applications is sphere-pac mixed carbide fuel. To support this development, it is necessary to devise analytical methods to assess and predict the behavior of fuel pins under irradiation conditions. This Note describes the modeling of the thermal aspect of this behavior. As a first step in treating a sphere-pac mixed carbide fuel pin, models for various physical phenomena have been developed and integrated to give the overall fuel pin response. Included are descriptions for the thermal conductivity of the packed particle bed in its initial configuration and during restructuring, the sintering of fuel spheres leading to the restructuring within the pin, the temperature distribution, grain growth and porosity redistribution, gas release and free swelling, and the effect of the gas in the free volume of the pin. The models describing the various thermal components were incorporated into the computer program SPECKLE-I. In the absence of a detailed mechanism analysis, restrictive assumptions were made. While the code is a limited first step in the analysis, results from SPECKLE-I were compared with several pin irradiations. Calculations of gas pressure and composition, fractional gas release, and the extent of initial-stage restructuring within the pin were compared to measurements. Initial results generally agree to within 20% or better for the parameters investigated.