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Title: Graphite Oxidation Thermodynamics/Reactions

Abstract

The vulnerability of graphite-matrix spent nuclear fuel to oxidation by the ambient atmosphere if the fuel canister is breached was evaluated. Thermochemical and kinetic data over the anticipated range of storage temperatures (200 to 400 C) were used to calculate the times required for a total carbon mass loss of 1 mgcm-2 from a fuel specimen. At 200 C, the time required to produce even this small loss is large, 900,000 yr. However, at 400 C the time required is only 1.9 yr. The rate of oxidation at 200 C is negligible, and the rate even at 400 C is so small as to be of no practical consequence. Therefore, oxidation of the spent nuclear fuel upon a loss of canister integrity is not anticipated to be a concern based upon the results of this study.

Authors:
Publication Date:
Research Org.:
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (US)
Sponsoring Org.:
USDOE Office of Environmental Management (EM) (US)
OSTI Identifier:
769038
Report Number(s):
DOE/SNF/REP-018
TRN: US0100741
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Sep 1998
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CARBON; CONTAINERS; GRAPHITE; KINETICS; NUCLEAR FUELS; OXIDATION; STORAGE; VULNERABILITY; GRAPHITE-MATRIX; SPENT NUCLEAR FUEL; CANISTER INTEGRITY; THERMODYNAMICS

Citation Formats

Propp, W.A.. Graphite Oxidation Thermodynamics/Reactions. United States: N. p., 1998. Web. doi:10.2172/769038.
Propp, W.A.. Graphite Oxidation Thermodynamics/Reactions. United States. doi:10.2172/769038.
Propp, W.A.. Tue . "Graphite Oxidation Thermodynamics/Reactions". United States. doi:10.2172/769038. https://www.osti.gov/servlets/purl/769038.
@article{osti_769038,
title = {Graphite Oxidation Thermodynamics/Reactions},
author = {Propp, W.A.},
abstractNote = {The vulnerability of graphite-matrix spent nuclear fuel to oxidation by the ambient atmosphere if the fuel canister is breached was evaluated. Thermochemical and kinetic data over the anticipated range of storage temperatures (200 to 400 C) were used to calculate the times required for a total carbon mass loss of 1 mgcm-2 from a fuel specimen. At 200 C, the time required to produce even this small loss is large, 900,000 yr. However, at 400 C the time required is only 1.9 yr. The rate of oxidation at 200 C is negligible, and the rate even at 400 C is so small as to be of no practical consequence. Therefore, oxidation of the spent nuclear fuel upon a loss of canister integrity is not anticipated to be a concern based upon the results of this study.},
doi = {10.2172/769038},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Sep 01 00:00:00 EDT 1998},
month = {Tue Sep 01 00:00:00 EDT 1998}
}

Technical Report:

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