Published 2004
| Version v1
Book
Codes and standards development for graphite-moderated nuclear reactors
Creators
- 1. Oak Ridge National Lab., TN (United States)
- 2. US Nuclear Regulatory Commission, Washington, DC (United States)
Description
This presentation will address the challenges involved in materials specification writing that involves acceptable processing methods, establishing minimum acceptable properties and properties ranges, establishing design codes that consider appropriately the inherent variability in properties of graphite, graphite failure criteria, and the inspection requirements for nuclear graphite before use and during service. The presentation will also include the status of activities related to the codes and standards development in the US and report on recent activities and directions in the ASTM and ASME standards and codes. (author)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-01601-5
- Imprint Title
- Basic studies in the field of high-temperature engineering
- Imprint Pagination
- 277 p.
- Journal Page Range
- p. 33-39
Conference
- Title
- 3. information exchange meeting
- Dates
- 11-12 Sep 2003
- Place
- Ibaraki-ken (Japan)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 35076786
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; FRACTURE MECHANICS; FUEL ELEMENTS; GRAPHITE; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; SPECIFICATIONS
- Descriptors DEC
- CARBON; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MECHANICS; MINERALS; NONMETALS; REACTOR COMPONENTS; REACTORS