Published May 2014 | Version v1
Journal article

Development of evaluation method with X-ray tomography for material property of IG-430 graphite for VHTR/HTGR

  • 1. HTGR Design Group Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Oarai-machi, Higashiibaraki-gun, Ibaraki-ken 311-1393 (Japan)
  • 2. Graphite and Carbon Materials Characterization Special Group, Nuclear Engineering Research Collaboration Center, Japan Atomic Energy Agency, 4002 Oarai-machi, Higashiibaraki-gun, Ibaraki-ken, 311-1393 (Japan)
  • 3. Atomic Energy Section, Production Division, Toyo Tanso Co., Ltd., 2791 Matsuzaki, Takuma-cho, Mitoyoshi, Kagawa-ken, 769-1102 (Japan)
  • 4. Department of HTTR, Japan Atomic Energy Agency, Higashiibaraki-gun, Ibaraki-ken 311-1393 (Japan)

Description

Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor (HTGR) which is a graphite-moderated and helium gas-cooled reactor. The HTGR is particularly attractive due to capability of producing high temperature helium gas, and its passive and inherent safety features. The Very High Temperature Reactor (VHTR) is one of the most promising candidates for the Generation-IV nuclear reactor systems. IG-110 graphite having high strength and resistance to oxidation is used in the HTTR of JAEA. IG-110 is a major candidate for the in-core graphite components of VHTR, too. From the standpoint of the safety at air ingress accident, it is important for graphite materials to have adequate resistance against oxidation damage. IG-430 graphite having higher strength and resistance to oxidation than IG-110 is an advanced candidate for the VHTR. Recently, X-ray tomography method is expected to apply the evaluation of neutron irradiation effects by measuring the irradiation-induced change of geometry of graphite grains and pores. This method is also applicable to evaluate the oxidation damage on graphite from the oxidation-induced change of grain/pore microstructures. In this study, in order to develop evaluation method for material properties and to evaluate the irradiation-induced property changes under higher neutron doses for IG-430, the oxidation and densification effects on elastic modulus of IG-430 were investigated. Moreover, the correlation of the microstructure based on the X-ray tomography images and the material properties was discussed. It was shown that the elastic modulus of the densified graphite depends on only the open pores and it is possible to evaluate the material properties of graphite by using X-ray tomography method. However, it is necessary to take into account of the change in the number and shape of closed pores in the grain to simulate the elastic modulus of the highly oxidized and irradiated materials by the homogenization analysis

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2013.11.053

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2013.11.053;
PII
S0029-5493(13)00638-9;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
271
Journal Page Range
p. 314-317
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)

Optional Information

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