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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Young Ryong Park, Nam Zin Cho
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 154-163
Technical Paper | doi.org/10.13182/NSE06-23
Articles are hosted by Taylor and Francis Online.
As the nuclear reactor core becomes more complex, heterogeneous, and geometrically irregular, the method of characteristics (MOC) is gaining popularity in neutron transport calculations. However, the long computing times require good acceleration methods. In this paper, the concept of coarse-mesh angular dependent rebalance (CMADR) acceleration is described and applied to the MOC calculation in x-y geometry. The method is based on the angular-dependent rebalance factors defined on coarse-mesh cell boundaries. A coarse-mesh cell may consist of several fine-mesh cells that can be heterogeneous and of mixed geometries with irregular or unstructured mesh shapes. The CMADR acceleration is tested on several test problems, including problems with strong material heterogeneity, and the results show that CMADR is very effective in reducing the number of iterations and the computing times of MOC calculations.