Published October 2007
| Version v1
Journal article
Oxidation performance of graphite material used in reactor
Creators
- 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy and New Energy Technology
Description
In high temperature gas-cooled reactor (HTGR), graphite is used as structural materials and moderator. During reactor operating, graphite oxidation which influences the safety and operation of reactor occurs due to the impurities in coolant or water ingress accident and air ingress accident which may be take place. In this paper, the oxidation process of graphite was introduced firstly, and then the factors which influence the graphite oxidation were analyzed and discussed. Some new questions for further studying were given. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 28
- Journal Issue
- 5
- Journal Page Range
- p. 50-53, 98
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 39075719
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BUILDING MATERIALS; COOLANTS; GRAPHITE; HTGR TYPE REACTORS; IMPURITIES; MODERATORS; OXIDATION; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CARBON; CHEMICAL REACTIONS; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; MINERALS; NONMETALS; OPERATION; REACTORS; SAFETY
Optional Information
- Notes
- 19 refs.