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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
NRC approves transfer of Vallecitos to North Star for D&D
By an order dated April 25, the Nuclear Regulatory Commission has approved the transfer of ownership of GE Hitachi Nuclear Energy’s Vallecitos Nuclear Center to NorthStar Group Services for nuclear decontamination, decommissioning, and environmental site restoration.
Shurong Ding, Yongzhong Huo
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 416-425
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3999
Articles are hosted by Taylor and Francis Online.
A metal-matrix dispersion fuel plate is considered. Taking account of the actual geometry, a special three-dimensional representative volume element is developed according to the particle distributions, which might characterize not only the macro deformation along the thickness but also the micro stress-strain fields. An elastoplastic analysis using the finite element method is carried out for the thermal-mechanical behaviors induced only by the thermal effects. The distributions of the thermal stresses at the fuel particles and the matrix are given, and the effects of the surface heat transfer coefficients, the heat generation rates of the fuel particles, and the degraded conductivities of the fuel particles along with the burnup on the stresses and the size variations of the plate thickness are investigated. The research results indicate that the internal stress distributions are not spherically symmetrical. With increasing surface heat transfer coefficients, the first principal stresses at the particles and the matrix both fall, and the thickness increments decrease. The first principal stresses at the fuel particles and the matrix both grow with increasing heat generation rates, and the thickness variations linearly increase. With decrease of the thermal conductivities of the fuel particles, the first principal stresses at the matrix increase, and the relative stresses at the particles decrease.