Published October 31, 2008 | Version v1
Journal article

Accumulation of thermal resistance in neutron irradiated graphite materials

Creators

  • 1. Materials Science and Technology Division, Oak Ridge National Laboratory, UT-Battele, P.O. Box 2008, Oak Ridge, TN 37831 (United States)

Description

A nuclear graphite, H451, and two high thermal conductivity graphite composites have been irradiated in the temperature range of 310-710 deg. C in the high flux isotope reactor and their thermal conductivities monitored in situ. Data were measured continuously up to a fast neutron dose of approximately 1 x 1025 n/m2 (E > 0.1 MeV). Data are interpreted in terms of the added thermal resistance and materials compared on this basis. Following this analysis it is shown that for the three materials studied, which have significantly different initial thermal conductivity values, the accumulation of thermal resistance is greater for the materials with lower initial thermal conductivity. Given that vacancies dominate phonon scattering at these irradiation temperatures and dose levels, these data clearly indicate that materials of higher perfection have a slower rate of stable vacancy accumulation during irradiation

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2008.07.017

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2008.07.017;
PII
S0022-3115(08)00403-0;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
381
Journal Issue
1-2
Journal Page Range
p. 76-82
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
7. International Graphite Specialists Meeting (INGSM); INGSM-8: 8. International Graphite Specialists Meeting (INGSM)
Acronym
INGSM-7
Dates
10-13 Sep 2006; 9-12 Sep 2007
Place
Oak Ridge, TN (United States); Sun City (South Africa)

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.