The oxidation effects of nuclear graphite during air-ingress accidents in HTGR

Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

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Author(s)

  • Wei-Hao Huang
  • Shuo-Cheng Tsai
  • I-Che Chiu
  • Chien-Hung Chen
  • Ji-Jung Kai

Detail(s)

Original languageEnglish
Pages (from-to)270-274
Journal / PublicationNuclear Engineering and Design
Volume271
Publication statusPublished - May 2014
Externally publishedYes

Abstract

This study consists of two main parts. The first part presents an experimental investigation of two types of nuclear graphite (IG-110, IG-430) at temperatures ranging from 700 to 1000 °C. Mercury porosimetry results and the quantification of pores in SEM/OM image show that the pores (pore diameter >4 μm) tended to grow into larger pores at temperatures >700 °C. The second part of this study presents a simulation of air-ingress accident. This experiment was conducted at temperatures ranging from 800 to 1000 °C with a flow rate of 0.35 L/min to simulate an air-ingress accident. Results indicate that IG-430 showed a tremendous improvement over IG-110 at medium temperature (

Citation Format(s)

The oxidation effects of nuclear graphite during air-ingress accidents in HTGR. / Huang, Wei-Hao; Tsai, Shuo-Cheng; Chiu, I-Che et al.
In: Nuclear Engineering and Design, Vol. 271, 05.2014, p. 270-274.

Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review