The implications of radiolytic graphite corrosion on AGR brick integrity
Creators
- 1. Central Electricity Generating Board, Gravesend (UK). Scientific Services Dept.
Description
The long term structural integrity of the major components of the Advanced Gas Cooled Reactor (AGR) is extremely important if economic and safe operation is to be ensured. In this context the integrity of the graphite core is vital in that it performs two prime functions, that of neutron moderation and of providing structural location of the fuel and control rods. Both of these functions must be maintained under all normal and fault conditions likely to be experienced throughout reactor life. The objective of this paper is to show how information from the study of the graphite/ CO2 reaction can be used in the complex assessment of brick integrity. A simplified review is given of the steps taken in such an assessment, including the types of loads experienced by bricks within the core and the graphite property changes associated with radiolytic corrosion. Finally, a number of modelling techniques are considered for simulating these property changes so that the resulting brick strength can be assessed. (author)
Additional details
Publishing Information
- Publisher
- Heyden.
- Imprint Place
- London
- ISBN
- 0 85501 449 0
- Imprint Title
- Gas chemistry in nuclear reactors and large industrial plant
- Imprint Pagination
- 295 p.
- Journal Page Range
- p. 155-163.
Conference
- Title
- Conference on gas chemistry in nuclear reactors and large industrial plant.
- Dates
- 21 - 24 Apr 1980.
- Place
- Salford, UK.
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 11569218
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; BRICKS; CARBON DIOXIDE; CORROSION; GRAPHITE; MASS TRANSFER; MATHEMATICAL MODELS; MODERATORS; RADIOLYSIS; REACTOR CORES; TENSILE PROPERTIES; YOUNG MODULUS
- Descriptors DEC
- BUILDING MATERIALS; CARBON; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; DECOMPOSITION; ELEMENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MECHANICAL PROPERTIES; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS