Design of core components

Nuclear Engineering and Design

Volumn 233, Issue 1-3, 2004, Pages 71-79

  Iyoku, Tatsuo ^a   Ueta, Shohei ^a   Sumita, Junya ^a   Umeda, Masayuki ^a   Ishihara, Masahiro ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

GAS COOLED REACTORS; GRAPHITE; HEAT RESISTANCE; HELIUM; RESEARCH AND DEVELOPMENT MANAGEMENT; SILICON CARBIDE; STRESS ANALYSIS;

CORE COMPONENTS; FUEL BLOCKS; REACTIVITY CONTROL EQUIPMENT;

HIGH TEMPERATURE REACTORS;

EID: 10644289571     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.07.012     Document Type: Conference Paper

References (12)

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4. Iyoku, T., et al., 1991a. Graphite core structures and their structural design criteria in the HTTR. Nucl. Eng. Des. 132, 23-30.
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10. Saito, S., et al., 1994. Design of High Temperature Engineering Test Reactor (HTTR). Japan Atomic Energy Research Institute Report. JAERI-1332.
11. Sawa, K., Tobita, T., et al., 1999. Fabrication of the first-loading fuel of the high temperature engineering test reactor. J. Nucl. Sci. Technol. 36, 683-690.
12. Sawa, K., Ueta, S., et al., 2004. Research and Development on HTGR fuel in the HTTR project. Nucl. Eng. Des. 233, 163-172.