Published October 2004
| Version v1
Journal article
Principle design and data of graphite components
- 1. Office of Planning, Japan Atomic Energy Research Institute, 14-1 Suehirocho, Kashiwa-shi Chiba-ken 277-0842 (Japan)
- 2. Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute, 3607 Narita, Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1394 (Japan)
- 3. Ibaraki Study Center, University of the Air c/o Ibaraki University, 2-1-1 Bunkyo, Mito-shi, Ibaraki-ken 310-0056 Japan (JP)
Description
The High Temperature Engineering Test Reactor (HTTR) constructed by Japan Atomic Energy Research Institute (JAERI) is a graphite-moderated and helium-gas-cooled reactor with prismatic fuel elements of hexagonal blocks. The reactor internal structures of the HTTR are mainly made up of graphite components. As well known, the graphite is a brittle material and there were no available design criteria for brittle materials. Therefore, JAERI had to develop the design criteria taking account of the brittle fracture behavior. In this paper, concept and key specification of the developed graphite design criteria is described, and also an outline of the quality control specified in the design criteria is mentioned
Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2004.08.012;
- PII
- S0029-5493(04)00255-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 233
- Journal Issue
- 1-3
- Journal Page Range
- p. 251-260
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36054294
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BRITTLENESS; FRACTURES; FUEL ELEMENTS; GRAPHITE; HTTR REACTOR; QUALITY CONTROL; SPECIFICATIONS
- Descriptors DEC
- CARBON; CONTROL; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FAILURES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; MINERALS; NONMETALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS
Optional Information
- Copyright
- Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.