Diffusion of cesium and iodine in compressed IG-110 graphite compacts
Source abstract
Abstract
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 1079–1290 K temperature range, and compared them to those obtained in as-received IG-110.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Graphite, nuclear technology, radiation studies · Nuclear Materials and Properties · Nuclear reactor physics and engineering
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References (13)
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