Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)

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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 ... continued below

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106 pages

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PAJUNEN, A.L. September 20, 2000.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 39 times , with 5 in the last month . More information about this report can be viewed below.

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Description

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. The correlation selection basis will consider input from all available sources that indicate the oxidation rate of uranium fuel, including the literature data, confirmatory experimental studies, and fuel element observations. Trimble (2000) summarizes literature data and the results of laboratory scale experimental studies. This document combines the information in Trimble (2000) with larger scale reaction observations to describe uranium oxidation rate correlations applicable to conditions of interest to the SNF Project.

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106 pages

Notes

INIS; OSTI as DE00804749

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  • Other Information: PBD: 20 Sep 2000

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  • Report No.: HNF-4165, Rev.1
  • Grant Number: AC06-96RL13200
  • DOI: 10.2172/804749 | External Link
  • Office of Scientific & Technical Information Report Number: 804749
  • Archival Resource Key: ark:/67531/metadc740692

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  • September 20, 2000

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  • Oct. 18, 2015, 6:40 p.m.

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  • May 3, 2016, 2:23 p.m.

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PAJUNEN, A.L. Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM), report, September 20, 2000; United States. (digital.library.unt.edu/ark:/67531/metadc740692/: accessed November 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.