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Preliminary Study on Thermal-Load Fluctuation Test Using HTTR

[+] Author Affiliations
Daisuke Tochio, Yosuke Shimazaki, Kazuhiko Iigaki, Shigeaki Nakagawa, Shoji Takada, Nariaki Sakaba, Kazuhiro Sawa

Japan Atomic Energy Agency, Ibaraki, Japan

Paper No. ICONE21-16082, pp. V002T05A034; 8 pages
doi:10.1115/ICONE21-16082
From:
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5579-9
  • Copyright © 2013 by ASME

abstract

JAEA has designed and developed a commercial very high temperature reactor hydrogen cogeneration system named GTHTR300C. JAEA has investigated that a hydrogen production facility is treated as not a reactor grade facility but a general industrial plant grade facility. The reactor plant system should be designed absorbing the disturbance under AOO and becoming to steady state in the case that thermal-load of the facility is fluctuated or lost. Also, high-accuracy plant dynamics code should be developed to design the GTHTR300C.

In order to demonstrate continuing the reactor operation in if the AOO is occurred in the hydrogen production facility and to obtain the validation data for high-accuracy plant dynamics code, the thermal-load fluctuation tests were planned using the HTTR in JAEA. In this study, it is concluded that the thermal-load fluctuation tests can be carried out without reactor scram and without modification of the HTTR facility and that the test data for validation of the code can be obtained sufficiently.

Copyright © 2013 by ASME
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