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Title: AN ASSESSMENT OF THE CARBON TRANSPORT PROBLEM IN HIGH TEMPERATURE GAS COOLED REACTORS. Project DRAGON.

Technical Report ·
OSTI ID:4136198

In a high temperature helium cooled, graphite moderated reactor the inleakage of oxidising impurities constitutes a major problem. Graphite corrosion and carbon deposition may reduce considerably the effective lifetime of the core fuel elements and heat exchangers. In order to minimise this problem the oxidising impurities must be kept in certain limits. The present report tries to explain and to detail the carbon transport problem by assessing the importance of the different parameters. Equations are presented which relate the maximum permissible corrosion to the attack of the fuel particle coating. Other expressions allow to estimate the purification flow or the maximum permissible water inleakage required to avoid excessive graphite corrosion and carbon deposition, as function of corrosion rates, heat exchanger reactivity, total flow, thermodynamic equilibria, etc. Some thoughts have also been extended to show how the concentrations of the reactants can vary as function of time when constant along the coolant circuit (Appendix 3). This might be of particular interest during reactor start-up. (auth)

Research Organization:
Atomic Energy Establishment, Winfrith (England)
NSA Number:
NSA-24-040973
OSTI ID:
4136198
Report Number(s):
DP-Report-330
Resource Relation:
Other Information: UNCL. Orig. Receipt Date: 31-DEC-70
Country of Publication:
United Kingdom
Language:
English