Fuel temperature analysis method for channel-blockage accident in HTTR

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

Research output: Contribution to journalArticle

4 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

Fingerprint

engineering test reactors
High temperature engineering
accidents
accident
Accidents
engineering
hydraulics
temperature
Temperature
Hydraulics
nuclear fuel elements
damage
Helium
integrity
helium
safety
thermal analysis
Demonstrations
reactors
reactor

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

Cite this

Fuel temperature analysis method for channel-blockage accident in HTTR. / Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Kiso, Yoshihiro; Hayakawa, Hitoshi.

In: Nuclear Engineering and Design, Vol. 150, No. 1, 02.09.1994, p. 69-80.

Research output: Contribution to journalArticle

Maruyama, So ; Fujimoto, Nozomu ; Sudo, Yukio ; Kiso, Yoshihiro ; Hayakawa, Hitoshi. / Fuel temperature analysis method for channel-blockage accident in HTTR. In: Nuclear Engineering and Design. 1994 ; Vol. 150, No. 1. pp. 69-80.
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