Fuel temperature analysis method for channel-blockage accident in HTTR

So Maruyama, Nozomu Fujimoto, Yukio Sudo, Yoshihiro Kiso, Hitoshi Hayakawa

Research output: Contribution to journalArticlepeer-review

6 Citations (Scopus)

Abstract

During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.

Original languageEnglish
Pages (from-to)69-80
Number of pages12
JournalNuclear Engineering and Design
Volume150
Issue number1
DOIs
Publication statusPublished - Sep 2 1994
Externally publishedYes

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

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