The behaviour of CAGR moderator and sleeve graphites radiolytically oxidised to high weight loss in inhibited coolant gas compositions
Creators
- 1. UKAEA Northern Research Labs., Springfields (UK)
- 2. UKAEA Northern Research Labs. Windscale, Seascale (UK)
Description
Gilsocarbon graphites were irradiated to high weight losses in three different CO2 based coolants. The experimental data is tested against a model which interprets the gas phase chemistry and pore geometry and allows weight loss and gas flow properties to be calculated. The observed changes of oxidation rate with dose were successfully predicted from the model. An empirical relationship was also derived which was shown to fit data for moderator, sleeve and special pore structure graphites. Changes in graphite permeability and diffusivity were predicted by the model, and also by other simplified, more approximate methods. The model based upon the measured transport pore spectrum was shown to be the best with other methods proving adequate to moderate doses. (author)
Additional details
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (UK)
- ISBN
- 0 7277 1306 X
- Imprint Title
- Materials for nuclear reactor core applications. 2 v.
- Imprint Pagination
- 454 p.
- Journal Page Range
- v. 1 p. 105-112.
Conference
- Title
- International conference on materials for nuclear reactor core applications.
- Dates
- 27-29 Oct 1987.
- Place
- Bristol (UK).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 20016567
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; COOLANTS; GAS FLOW; GRAPHITE; MATHEMATICAL MODELS; OXIDATION; PERMEABILITY; POROUS MATERIALS; RADIOLYSIS; WEIGHT
- Descriptors DEC
- CARBON; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; DECOMPOSITION; ELEMENTS; ENRICHED URANIUM REACTORS; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; NONMETALS; RADIATION EFFECTS; REACTORS