Development of the cooling technology on TRU fuel pin bundle during fuel fabrication process (4) steady state cooling test of full mock up fuel pin bundle

Kunihiro Itoh, Kazuo Ikeda, Koichi Hishida, Akira Yamaguchi, Takashi Takata, Yuichiro Manabe

研究成果: Conference contribution

抄録

The development of the fast reactor cycle is being preceded in Japan to utilize plutonium and trans-uranium materials which come from the simplified PUREX reprocessing. But the TRU fuel bundle generates heat due to fission of TRU during the fabrication process of the wire wrapped Fast Breeder Reactor (FBR) fuel pin bundle. Then it is a big issue to develop an efficient cooling system for the horizontally laid bundle and to clarify its thermal behavior. Then in this paper the steady state full mock up test results are described. Inlet air velocity and heat generation rate were varied in the tests as the parameter. Then it is ascertained that the fuel can be cooled under the 473 K which is the criterion for the steady state cooling of this study to keep cladding soundness. The temperature and velocity fields of the bundle upper side were also measured by moving thermocouples to vertical and horizontal directions, by the infrared thermometer and by PIV (Particle Image Velocimetry). Then the temperature and velocity fields at outlet region are clarified.

本文言語English
ホスト出版物のタイトルInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
出版社Atomic Energy Society of Japan
ページ1806-1812
ページ数7
ISBN(電子版)9781617386084
出版ステータスPublished - 2009
外部発表はい
イベントInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 - Shinjuku, Tokyo, Japan
継続期間: 2009 5 102009 5 14

出版物シリーズ

名前International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
3

Other

OtherInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
国/地域Japan
CityShinjuku, Tokyo
Period09/5/1009/5/14

ASJC Scopus subject areas

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学

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