SOME ASPECTS OF CARBON TRANSPORT IN HIGH TEMPERATURE GAS COOLED REACTORS. Project DRAGON.
The corrosion of graphite by small quantities of oxidising impurities in helium has been studied both out-of-pile and an in-pile loop. To provide more data and to avoid interference from side reactions with the materials of the loop, 0-14 labelled graphite samples have been used to supplement the information gained from normal gas analytical equipment. For the results obtained from the in-pile loop experiments a theoretical model is proposed which explains the large departure of the observed reaction rate from first order dependance on carbon dixode concentrations for the temperature range 250-900 deg C. Other aspects of graphite corrosion in a high temperature helium cooled graphite moderated reactor are briefly considered. Carbon deposition reactions on catalytically active surfaces have been studied experimentallly over the temperature range 200-700 deg C. Gas quilibria limiting the system for iron surfaces are considered and found to explain the experimentally observed distribution of deposited carbon with respect to temperature. The effects of carbon deposition on steel surfaces and the nature of the deposited carbon have been studied. Observed rates of carbon deposition when extrapolated to power reactor conditions indicate the possibility of large increases in graphite corrosion rates caused by regeneration of oxidising impurities, if no special measures are taken. The paper presents a new mathematical approach to design and operation aspects of carbon transport in high temperature and gas cooled reactors. (auth)
- Research Organization:
- Atomic Energy Establishment, Winfrith, England (United Kingdom)
- NSA Number:
- NSA-24-043756
- OSTI ID:
- 4096453
- Report Number(s):
- DP-Report-365; CONF-650632-20
- Resource Relation:
- Conference: 7th Biennial Conference on Carbon, Cleveland, OH (US), 21-25 Jun 1965; Related Information: OECD High Temperature Reactor Project Dragon Report. Now open access.
- Country of Publication:
- United Kingdom
- Language:
- English
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Related Subjects
N30210 - Metals
Ceramics
& Other Materials-Ceramics & Cermets-Corrosion & Erosion & Surface Phenomena
CARBON
CORROSION
DEPOSITS
DRAGON
FUEL ELEMENTS
GRAPHITE
MATHEMATICS
PERFORMANCE
POWER REACTORS
REACTOR CORE
TRANSPORT
GRAPHITE/properties in gas cooled reactor core components
chemical and physical
HELIUM/corrosive effects on graphite
effects of oxidizing impurities on
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/core components in
corrosion and properties of graphite
GRAPHITE/corrosion by helium coolants
effects of oxidizing impurities on
CARBON/transport in Dragon Reactor
mathematical analysis of