Art

J-GLOBAL ID：201402213902042100   Reference number：14A1455666

Validation and application of thermal hydraulic system code for analysis of helically coiled heat exchanger in high-temperature environment

高温環境におけるヘリカルコイル型熱交換器分析用の熱流体力学システムコードの検証及び応用

Author (5)： SATO Hiroyuki (Japan Atomic Energy Agency, Ibaraki, JPN) ,  OHASHI Hirofumi (Japan Atomic Energy Agency, Ibaraki, JPN) ,  NAKAGAWA Shigeaki (Japan Atomic Energy Agency, Ibaraki, JPN) ,  TACHIBANA Yukio (Japan Atomic Energy Agency, Ibaraki, JPN) ,  KUNITOMI Kazuhiko (Japan Atomic Energy Agency, Ibaraki, JPN)
Material： Journal of Nuclear Science and Technology  (J Nucl Sci Technol)
Volume： 51  Issue： 11-12  Page： 1324-1335  Publication year： Nov. 2014 
JST Material Number： W2314A  ISSN： 0022-3131  Document type： Article
Article type： 原著論文  Country of issue： United Kingdom (GBR)  Language： ENGLISH (EN)

Thesaurus term： *HTGR type reactor ,  thermal-hydraulic performance ,  heat exchanger ,  *production ,  manufacturing ,  *hydrogen ,  computer code ,  chemical process ,  thermochemical reaction ,  application program ,  transient analysis ,  *safety analysis ,  reactor safety
Semi thesaurus term： ヘリカルコイル型熱交換器 ,  hydrogen producing ,  computational fluid dynamics code ,  High Temperature Engineering Test Reactor ,  intermediate heat exchanger ,  Iodine-Sulfur Process ,  RELAP5

JST classification (3)： Safety of gas-cooled reactors  (MD06030S) ,  Heat source for process heating  (MD07030Z) ,  Manufacturing of gaseous fuels  (YE02030F)

Reference (21)：

• Inagaki Y, Koiso H, Takumi H, Ioka I, Miyamoto Y. Thermal hydraulic study on a high-temperature gas-gas heat exchanger with helically coiled tube bundles. Nucl Eng Des. 1998;185:141-151.
• Hirano M, Hada K. Development of THYDE-HTGR: computer code for transient thermal-hydraulics of high-temperature gas-cooled reactor. Tokyo: Japan Atomic Energy Research Institute; 1990, JAERI-M 90-071.
• Saito S, Tanaka T, Sudo Y, Baba O, Shindo M, Shioawa S, Mogi H, Okubo M, Ito N, Shindo R, Kobayashi N, Kurihara R, Hayashi K, Hada K, Kurata Y, Yamashita K, Kawasaki K, Iyoku T, Kunitomi K, Maruyama S, Ishihara M, Sawa K, Fujimoto N, Murata I, Nakagawa S, Tachibana Y, Nishihara T, Oshita S, Shinozaki M, Takeda T, Sakaba N, Saikusa A, Tazawa Y, Fukaya Y, Nagahori H, Kikuchi T, Kawaji S, Isozaki M, Matsuzaki S, Sakama I, Hara K, Ueda N, Kokusen S. Design of high temperature engineering test reactor (HTTR). Tokai (Japan): Japan Atomic Energy Research Institute; 1994, JAERI 1332.
• Tochio D, Nakagawa S. Thermal performance of intermediate heat exchanger during high-temperature continuous operation in HTTR. J Nucl Sci Technol. 2011;48:1361-1368.
• Takeda T, Nakagawa S, Honma F, Takada E, Fujimoto N. Safety shutdown of the high temperature engineering test reactor during loss of off-site electric power simulation test. J Nucl Sci Technol. 2002;39:986-995.

Terms in the title (7)： 高温環境 ,  ヘリカルコイル ,  熱交換器 ,  分析 ,  熱流体力学 ,  検証 ,  応用