Corrosion of U sub x Zr sub 1-x C sub 1-y nuclear fuel materials in hydrogen gas at high pressures and temperatures

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This paper describes the thermodynamics and kinetics of the corrosion of U{sub x}Zr{sub 1-x}C{sub 1-y} in hydrogen gas. It describes how corrosion rates are influenced by variables such as pressure, temperature, and gas flow rate. A model is developed which agrees with experimental steady state corrosion rates at 1 atm between 2670 and 3100 K. Under these conditions the corrosion flux is rate limited by the vapor phase transport of Zr(g) away from the solid surface to the bulk gas stream where the partial pressure of Zr(g) is determined by the congruently vaporizing surface composition. Extrapolation of the model to ... continued below

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Pages: (7 p)

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Butt, D.P. January 1, 1992.

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Description

This paper describes the thermodynamics and kinetics of the corrosion of U{sub x}Zr{sub 1-x}C{sub 1-y} in hydrogen gas. It describes how corrosion rates are influenced by variables such as pressure, temperature, and gas flow rate. A model is developed which agrees with experimental steady state corrosion rates at 1 atm between 2670 and 3100 K. Under these conditions the corrosion flux is rate limited by the vapor phase transport of Zr(g) away from the solid surface to the bulk gas stream where the partial pressure of Zr(g) is determined by the congruently vaporizing surface composition. Extrapolation of the model to higher pressures indicates that Zr(g) transport should also be rate limiting at higher pressures but the corrosion rate should decrease with increased total pressure due to reduced gaseous diffusion rates. The model predicts that the corrosion rate will increase as the square root of gas velocity for a given temperature and pressure. Calculations demonstrating the effects of gas velocity are in agreement with experimental studies. The addition of hydrocarbons to the hydrogen gas stream is predicted to decrease the corrosion rates significantly.

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Pages: (7 p)

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OSTI; NTIS; GPO Dep.

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  • World space congress, Washington, DC (United States), 28 Aug - 5 Sep 1992

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  • Other: DE92013430
  • Report No.: LA-UR-92-1377
  • Report No.: CONF-920879--1
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5282298
  • Archival Resource Key: ark:/67531/metadc1063764

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 1992

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  • Feb. 4, 2018, 10:51 a.m.

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  • May 21, 2018, 3:47 p.m.

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Butt, D.P. Corrosion of U sub x Zr sub 1-x C sub 1-y nuclear fuel materials in hydrogen gas at high pressures and temperatures, article, January 1, 1992; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1063764/: accessed August 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.