Published August 1, 2016 | Version v1
Journal article

Diffusion of cesium and iodine in compressed IG-110 graphite compacts

  • 1. Department of Chemistry, University of Missouri, 125 Chemistry Building, Columbia, MO 65211 (United States)
  • 2. University of Missouri Research Reactor Center, University of Missouri, 1513 Research Park Dr., Columbia, MO 65211 (United States)
  • 3. Nuclear Science and Engineering Institute, University of Missouri, E2433 Lafferre Hall, Columbia, MO 65211 (United States)

Description

Nuclear graphite grade IG-110 is currently used in the High Temperature Engineering Test Reactor (HTTR) in Japan for certain permanent and replaceable core components, and is a material of interest in general. Therefore, transport parameters for fission products in this material are needed. Measurement of diffusion through pressed compacts of IG-110 graphite is experimentally attractive because they are easy to prepare with homogeneous distributions of fission product surrogates. In this work, we measured diffusion coefficients for Cs and I in pressed compacts made from IG-110 powder in the 1079–1290 K temperature range, and compared them to those obtained in as-received IG-110. - Highlights: • A method for analysis of fission product diffusion in graphite by ICP-MS was applied to pressed IG-110 graphite compacts containing cesium and iodine. • Diffusion coefficients for cesium and iodine were obtained. • The measurement design simulates HTGR conditions of high temperature and flowing helium.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2016.04.024

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2016.04.024;
PII
S0022-3115(16)30139-8;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
476
Journal Page Range
p. 30-35
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.