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

Optional Information

Copyright
Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.