THE CORROSION OF GRAPHITE IN AN H.T.G.R. Project DRAGON
- Author
- Pointud, M. L.
- Published
- United Kingdom : [publisher not identified], 1963.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1963. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- de Bruijn, H. and Valette, L.
- Summary
- Because of the unavoidable small amounts of oxidising impurities present in helium, which is used as a coolant in an HTGR, corrosion of the core graphite can be expected. First of all we are dealing with an overall corrosion of the outer surface of the graphite fuel rods which will lead to dimensional changes of the coolant channels. In order to avoid appreciable changes of reactivity or changes of the heat transfer characteristics of the coolant channels no more corrosion can be allowed than equivalent to the removal of 0.5 mm. Apart from this we have to take into account possible corrosion of the interior of the graphite components of the core. Corrosion rates, research efforts and experimental results are reported.
- Report Numbers
- DP-Report-130; CONF-630103-20
- Other Subject(s)
- Coolants
- Corrosion
- Dragon
- Graphite/ corrosion by high temperature htgr helium coolant, mechanisms of.
- Helium
- Helium/corrosive effects on htgr graphite
- High temperature
- High- temperature gas-cooled reactor experiment/coolant for, corrosive effects on graphite
- N30210 -metals, ceramics, & other materials-ceramics & cermets-corrosion & erosion & surface phenomena
- N38100 -power reactor development
- Reactors
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- NSA number: NSA-24-042177
OSTI Identifier 4099745
Research organization: Atomic Energy Establishment, Winfrith (England).
View MARC record | catkey: 44538039