| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 9824426 | Annals of Nuclear Energy | 2005 | 26 Pages |
Abstract
In this paper the development and verification of 1D version DYN1D-MSR of the code is described. The code has been validated with the experimental data gained from the molten salt reactor experiment performed in the Oak Ridge and after the validation it was applied to several typical transients (overcooling of fuel at the core inlet, reactivity insertion, and the fuel pump trip).
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Authors
Jiri Krepel, Ulrich Grundmann, Ulrich Rohde, Frank-Peter Weiss,