Projects per year
Abstract
Graphite, an attractive moderating material due to its unique characteristics, has been used in different reactor generations and is currently a candidate for future Generation IV high-temperature reactors and molten salt-cooled reactors. The graphite material is complex and its properties are dependent on the length scale. Furthermore, the bulk graphite properties are dependent on many factors, such as manufacturing, grain size, and operational environment. These properties also change over time due to irradiation. Based on experience gained from different current graphite moderated reactors, referring to both past experience and data more recently obtained in various EU Framework projects, this chapter introduces the basics of graphite as a nuclear material for application to Generation IV reactors. Current procedures and understanding of graphite manufacturing, material properties models, component structural integrity assessment, and waste management are presented to help future reactor designers. Specific issues related to high-temperature nuclear graphite are also discussed.
Original language | English |
---|---|
Title of host publication | Structural Materials for Generation IV Nuclear Reactors |
Editors | Pascal Yvon |
Publisher | Woodhead Publishing |
Pages | 495–532 |
Number of pages | 38 |
ISBN (Electronic) | 978-0-08-100912-3 |
ISBN (Print) | 978-0-08-100906-2 |
DOIs | |
Publication status | Published - 16 Sept 2016 |
Publication series
Name | Woodhead Publishing Series in Energy |
---|
Keywords
- Generation IV
- Gilsocarbon
- Graphite
- Irradiation
- Nuclear reactor
- Waste
Fingerprint
Dive into the research topics of 'Graphite as a core material for Generation IV nuclear reactors'. Together they form a unique fingerprint.Projects
- 1 Finished
-
Nuclear Energy University Programs (NEUP) US/UK Collaborative Funding Opportunity
Jones, A. (PI), Marsden, B. (CoI) & Sharrad, C. (CoI)
1/12/17 → 30/11/20
Project: Research