| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 6761612 | Nuclear Engineering and Design | 2015 | 12 Pages |
Abstract
SOCRAT/V3 computer modeling code was used for calculation of basic thermal hydraulic, oxidation and thermal mechanical behavior during all phases of the experiment. The calculated results are in a good agreement with experimental data which justifies the adequacy of modeling capabilities of SOCRAT code system.
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Authors
A. Vasiliev, J. Stuckert,