科技报告详细信息
Uranium Oxidation Rate Summary for the Spent Nuclear Fuel Project (OCRWM).
Pajunen, A. L.
Technical Information Center Oak Ridge Tennessee
关键词: Spent nuclear fuels;    Uranium oxidation;    Reaction rates;    System design;    Radioactive waste facilities;   
RP-ID  :  DE2003804749
学科分类:工程和技术(综合)
美国|英语
来源: National Technical Reports Library
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【 摘 要 】

The purpose of this document is to summarize the uranium oxidation reaction rate information developed by the Hanford Spent Nuclear Fuel (SNF) Project and describe the basis for selecting reaction rate correlations used in system design. The selection basis considers the conditions of practical interest to the fuel removal processes and the reaction rate application during design studies. Since the reaction rate correlations are potentially used over a range of conditions, depending of the type of evaluation being performed, a method for transitioning between oxidation reactions is also documented. The document scope is limited to uranium oxidation reactions of primary interest to the SNF Project processes. The reactions influencing fuel removal processes, and supporting accident analyses, are: uranium-water vapor, uranium-liquid water, uranium-moist air, and uranium-dry air.

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