Principle design and data of graphite components

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 compon...

Full description

Saved in:
Bibliographic Details
Published inNuclear engineering and design Vol. 233; no. 1; pp. 251 - 260
Main Authors Ishihara, Masahiro, Sumita, Junya, Shibata, Taiju, Iyoku, Tatsuo, Oku, Tatsuo
Format Journal Article
LanguageEnglish
Published Elsevier B.V 01.10.2004
Online AccessGet full text

Cover

More Information
Summary: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.
Bibliography:ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2004.08.012