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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Samet Y. Kadioglu, Dana A. Knoll, Cassiano de Oliveira
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 132-143
Technical Paper | doi.org/10.13182/NSE09-07
Articles are hosted by Taylor and Francis Online.
Coupling neutronics to thermomechanics is important for the analysis of fast burst reactors because the criticality and safety study of fast burst reactors depends on the thermomechanical behavior of fuel materials. For instance, the shutdown mechanism or the transition between supercritical and subcritical states is driven by the fuel material expansion or contraction. The material expansion is due to the temperature gradient that results from fission power. In this paper, we introduce a numerical model for coupling of neutron diffusion and thermomechanics in fast burst reactors. The goal is to have a better understanding of the relation between the reactivity insertion and the thermomechanical response of fuel materials. We perform a nondimensional analysis of the coupled system that provides insight into the behavior of the transient. We also provide a semianalytical solution model to the coupled system for partial verification of our numerical solutions. We studied material behavior corresponding to different levels of reactivity insertion.