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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
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.