Development of the cooling technology on TRU fuel pin bundle during fuel fabrication process: (3) Development of analytical tool

Takashi Takata, Akira Yamaguchi, Koichi Hishida, Taichiro Kuroda, Kunihiro Itoh, Kazuo Ikeda

Research output: Chapter in Book/Report/Conference proceedingConference contribution

5 Citations (Scopus)

Abstract

In the trans-uranium (TRU) fuel bundle fabrication process, a fuel pin is spirally wrapped with a thin wire in order to keep a clearance between fuel pins and is laid horizontally. Air flows into the gaps vertically across the pin bundle so as to suppress temperature increase due to decay heat of TRU during the fabrication. From a safety point of view, an effective cooling is of importance. In the present study, an analytical tool, based on a subchannel thermal-hydraulics simulation, has been developed to investigate the thermal-hydraulic behavior and to predict the maximum temperature and the temperature distribution inside the fuel bundle.

Original languageEnglish
Title of host publicationAmerican Nuclear Society - International Conference on Advances in Nuclear Power Plants, ICAPP 2008
Pages1916-1922
Number of pages7
Publication statusPublished - 2008 Dec 1
EventInternational Conference on Advances in Nuclear Power Plants, ICAPP 2008 - Anaheim, CA, United States
Duration: 2008 Jun 82008 Jun 12

Publication series

NameInternational Conference on Advances in Nuclear Power Plants, ICAPP 2008
Volume3

Other

OtherInternational Conference on Advances in Nuclear Power Plants, ICAPP 2008
CountryUnited States
CityAnaheim, CA
Period08/6/808/6/12

ASJC Scopus subject areas

  • Fuel Technology
  • Nuclear Energy and Engineering

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    Takata, T., Yamaguchi, A., Hishida, K., Kuroda, T., Itoh, K., & Ikeda, K. (2008). Development of the cooling technology on TRU fuel pin bundle during fuel fabrication process: (3) Development of analytical tool. In American Nuclear Society - International Conference on Advances in Nuclear Power Plants, ICAPP 2008 (pp. 1916-1922). (International Conference on Advances in Nuclear Power Plants, ICAPP 2008; Vol. 3).