Principle design and data of graphite components

Nuclear Engineering and Design

Volumn 233, Issue 1-3, 2004, Pages 251-260

  Ishihara, Masahiro ^a   Sumita, Junya ^a   Shibata, Taiju ^a   Iyoku, Tatsuo ^a   Oku, Tatsuo ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b OPEN UNIVERSITY OF JAPAN   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BRITTLENESS; DUCTILITY; FRACTURE TESTING; GAS COOLED REACTORS; HIGH TEMPERATURE ENGINEERING; QUALITY CONTROL; STRAIN; STRESS ANALYSIS;

FUEL ELEMENTS; GRAPHITE COMPONENTS; HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR); STRESS-STRAIN RESPONSE;

GRAPHITE;

EID: 10644257621     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.08.012     Document Type: Conference Paper

References (7)

1. Ho, F., et al., 1983. Biaxial failure surface of 220 and PGX graphites. SMiRT 7L4/6, Chicago, USA.
2. Kikuchi, K., et al., 1984. Failure of graphite short bars with hemispherical seats. Eng. Fract. Mech. 19, 1013-1024.
3. Yoda, S., et al., 1984. Effects of oxidation on tensile and compressive deformation behavior for nuclear grade isotropic graphite. Intern. Carbon Conf. 84, Bordeaux, France.
4. Price, R.J., Beavan, L.A., 1981. Strength of nonuniformly oxidized PGX graphite. GA-A16270.
5. Eto, M., Growcock, F.B., 1984. Effect of prestress and stress on strength and oxidation rate of nuclear graphite. NUREG/CR-2316.
6. Schmidt, A., 1989. Design methods and criteria for graphite components. Jül-Conf-71.
7. Iyoku, T., et al., 1991. Graphite core structures and their structural design criteria in the HTTR. Nucl. Eng. Des. 132, 23-30.