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Title: Oxidation behaviors of matrix-grade graphite during water vapor ingress accidents for high temperature gas-cooled reactors

Journal Article · · Carbon

Water ingress into cores of high temperature gas-cooled reactors (HTGRs) can cause serious safety problems in graphitic components, especially for matrix graphite, which is more vulnerable than nuclear graphite. Here in this study, oxidation behaviors of a matrix-grade graphite, ARB-B1, were investigated under simulated water ingress accidental conditions. The oxidation tests were conducted in water vapor/helium mixed atmospheres at elevated temperatures up to 1200 °C. Oxidation rates and activation energy were evaluated by mass loss measurements. The activation energy was 121.5 kJ/mol in the considered temperature range, indicating only one oxidation regime-in-pore diffusion assisted by cracks. The cracks originated from the fabrication process, acting as penetration paths for the oxidant, played an important role in the oxidation behaviors. Ungraphitized binder oxidation occurred at all temperatures, while apparent oxidation of filler particles started from 1100 °C. Moreover, oxidation effects on compressive properties and hardness of the matrix graphite were discussed in terms of oxidized microstructures. This first detailed study on matrix graphite oxidation in water vapor provides important kinetics knowledge and microstructural and mechanical data for accidental scenarios of HTGRs as well as for development of new matrix graphite materials.

Research Organization:
Virginia Polytechnic Institute and State University (Virginia Tech), Blacksburg, VA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
NE0008808
OSTI ID:
1976906
Journal Information:
Carbon, Journal Name: Carbon Journal Issue: C Vol. 185; ISSN 0008-6223
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (43)

Transportvorgänge und Oberflächenreaktionen bei der Verbrennung graphitischen Kohlenstoffs: Transportvorgänge und Oberflächenreaktionen bei der Verbrennung graphitischen Kohlenstoffs journal March 1956
Effect of metallic impurities on the gasification of graphite in water vapor and hydrogen journal August 1974
Catalytic gasification of carbon with steam, carbon dioxide and hydrogen journal January 1977
Catalytic steam gasification of graphite: Effects of calcium, strontium, and barium with and without sulfur journal January 1979
Surface area and porosity of unmodified graphitic matrices A3-27 and A3-3 (1950) and oxidized matrix A3-3 (1950) journal January 1989
Moment-preserving thresolding: A new approach journal March 1985
Kinetics and mechanisms of the reaction of air with nuclear grade graphites: IG-110 journal February 1997
Thermal analysis of the oxidation of natural graphite: isothermal kinetic studies journal April 2001
The oxidation behavior of A3-3 matrix graphite journal April 2016
The effect of microstructure on air oxidation resistance of nuclear graphite journal August 2012
Beyond the classical kinetic model for chronic graphite oxidation by moisture in high temperature gas-cooled reactors journal February 2018
Effective gaseous diffusion coefficients of select ultra-fine, super-fine and medium grain nuclear graphite journal September 2018
Water vapor oxidation behaviors of nuclear graphite IG-110 for a postulated accident scenario in high temperature gas-cooled reactors journal August 2020
Experimental study on the oxidation of nuclear graphite and development of an oxidation model journal February 2006
Practical aspects for characterizing air oxidation of graphite journal October 2008
Penetration depth and transient oxidation of graphite by oxygen and water vapor journal September 2009
Pore structure development in oxidized IG-110 nuclear graphite journal November 2012
The thermal performance of fuel matrix material in a CO2 atmosphere journal November 2013
Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios journal March 2014
Oxidation rate of graphitic matrix material in the kinetic regime for VHTR air ingress accident scenarios journal August 2014
Oxidation of PCEA nuclear graphite by low water concentrations in helium journal October 2014
The relationship between microstructure and oxidation effects of selected IG- and NBG-grade nuclear graphites journal November 2014
Effects of air flow rate on the oxidation of NBG-18 and NBG-25 nuclear graphite journal August 2017
Understanding the reaction of nuclear graphite with molecular oxygen: Kinetics, transport, and structural evolution journal September 2017
Comparison of NBG-18, NBG-17, IG-110 and IG-11 oxidation kinetics in air journal March 2018
A study of the relationship between microstructure and oxidation effects in nuclear graphite at very high temperatures journal April 2018
Coated particle fuel: Historical perspectives and current progress journal March 2019
Comparison of oxidation behaviour of nuclear graphite grades at very high temperatures journal April 2020
Determination of preferential binder oxidation in HTGR matrix material subjected to high temperature steam journal February 2021
Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite journal February 2004
Effect of temperature on graphite oxidation behavior journal February 2004
Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR journal November 2008
Water-ingress analysis for the 200MWe pebble-bed modular high temperature gas-cooled reactor journal October 2010
Oxidation behavior of IG and NBG nuclear graphites journal January 2011
Preparation of spherical fuel elements for HTR-PM in INET journal October 2013
The oxidation effects of nuclear graphite during air-ingress accidents in HTGR journal May 2014
Correlation for steam–graphite reaction journal December 2014
Kinetics and Mechanisms of the Two Opposing Reactions of the Equilibrium CO + H 2 O = CO 2 + H 2 1 journal May 1954
Reactions between carbon and oxygen journal January 1951
Burn-off and Production of CO and CO 2 in the Oxidation of Nuclear Reactor-Grade Graphites in a Flow System journal December 1994
Effects of microstructure on the oxidation behavior of A3 matrix‐grade graphite journal September 2020
Comparison of Oxidation Behaviors of Different Grades of Nuclear Graphite journal September 2005
Experimental Study and Model Development on the Moisture Effect for Nuclear Graphite Oxidation journal November 2008