| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 7966168 | Journal of Nuclear Materials | 2015 | 7 Pages |
Abstract
An understanding of the transport of fission products in High Temperature Gas-Cooled Reactors (HTGRs) is needed for operational safety as well as source term estimations. We have measured diffusion coefficients of Cs in IG-110 by using the release method, wherein we infused small graphite spheres with Cs and measured the release rates using ICP-MS. Diffusion behavior was investigated in the temperature range of 1100-1300Â K. We have obtained: DCs=(1.0Ã10-7m2/s)exp-1.1Ã105J/molRT and, compared our results with those available in the literature.
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Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
L.M. Carter, J.D. Brockman, S.K. Loyalka, J.D. Robertson,