| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1564654 | Journal of Nuclear Materials | 2016 | 6 Pages |
Abstract
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 1079-1290Â K temperature range, and compared them to those obtained in as-received IG-110.
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Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
L.M. Carter, J.D. Brockman, J.D. Robertson, S.K. Loyalka,