Design Optimization of A generic Fissile Solution for Mo99 production using Electron Beam-based Neutron Generator using MCNP+CFD [electronic resource]

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Tác giả:

Ngôn ngữ: eng

Ký hiệu phân loại: 621.3 Electrical, magnetic, optical, communications, computer engineering; electronics, lighting

Thông tin xuất bản: Washington, D.C. : Oak Ridge, Tenn. : United States. National Nuclear Security Administration ; Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 2020

Mô tả vật lý: Size: 34 p. : , digital, PDF file.

Bộ sưu tập: Metadata

ID: 261808

 Molybdenum-99 (<
 sup>
 99<
 /sup>
 Mo) is a medical isotope used in 80% of all medical imaging procedures today. However, <
 sup>
 99<
 /sup>
 Mo is not directly administered to patients for imaging
  its decay product, technetium-99m (<
 sup>
 99<
 /sup>
 mTc), is a metastable isotope with a half-life of ~6 hours. Such a short half-life does not allow for production, separation, and application to a patient before decaying further. Therefore, the solution is to produce the precursor to <
 sup>
 99<
 /sup>
 mTc, <
 sup>
 99<
 /sup>
 Mo. <
 sup>
 99<
 /sup>
 Mo has a half-life of 66 hours, long enough to produce the material and send it to the desired location before it fully decays. Under National Nuclear Security Administration?s (NNSA) highly enriched uranium (HEU) minimization mission, the Material Management and Minimization (M3) office leads the Molybdenum-99 (Mo-99) program. A major goal of the Mo-99 program is to develop methods of producing <
 sup>
 99<
 /sup>
 Mo using low enriched uranium (LEU) opposed to the traditionally used HEU domestically in the U.S. Internationally, LEU is the new standard for use in research reactors and isotope production facility. In this study, we introduce a generic fissile solution system for <
 sup>
 99<
 /sup>
 Mo production facility meeting the design requirement of 1) LEU usage as fissile material and 2) subcritical fissile system coupled with a horizontal electron beam (E-beam) accelerator. The focus of this research is to optimize a fissile solution configuration for maximum <
 sup>
  99<
 /sup>
 Mo production yield using MCNP model, and ultimately implement the optimized design with computational fluid dynamics (CFD) model to understand thermal hydraulic behavior and solution convection characteristic. The report consists of two parts: 1) isotope yield calculation and criticality analysis with a wide range of parametric test matrix, and 2) thermal hydraulic analysis for solution mixing and cooling assessment.
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