Published May 2014 | Version v1
Journal article Metadata-only

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

Creators

  • 1. Department of Engineering and System Science, National Tsing Hua University, Taiwan (China)
  • 2. Department of Materials Science and Engineering, University of Tennessee, Knoxville, TN (United States)
  • 3. Institute of Nuclear Engineering and Science, National Tsing Hua University, Taiwan (China)

Description

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 (<800 °C). However, the advantages of IG-430 began to diminish when the temperature increased

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2013.11.047

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2013.11.047;
PII
S0029-5493(13)00632-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
271
Journal Page Range
p. 270-274
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
6. topical meeting on high temperature reactor technology
Acronym
HTR 2012
Dates
28 Oct - 1 Nov 2012
Place
Tokyo (Japan)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46023286
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AIR INFILTRATION; FLOW RATE; GRAPHITE; HTGR TYPE REACTORS; IMAGES; OXIDATION; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; SCANNING ELECTRON MICROSCOPY; TEMPERATURE RANGE 0273-0400 K
Descriptors DEC
ACCIDENTS; CARBON; CHEMICAL REACTIONS; ELECTRON MICROSCOPY; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MICROSCOPY; MINERALS; NONMETALS; REACTORS; SIMULATION; TEMPERATURE RANGE

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.