
Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)
Author(s) -
A. Pajunen
Publication year - 2000
Language(s) - English
Resource type - Reports
DOI - 10.2172/804749
Subject(s) - uranium , depleted uranium , uranium oxide , spent nuclear fuel , nuclear fuel , environmental science , reaction rate , radioactive waste , scope (computer science) , waste management , chemistry , nuclear engineering , nuclear chemistry , nuclear physics , computer science , engineering , physics , catalysis , biochemistry , programming language
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