| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1740956 | Progress in Nuclear Energy | 2011 | 10 Pages |
Abstract
The best-estimate coupled neutronic/thermal-hydraulics code, SIMULATE-3K (S3K), is used by many utilities, research institutes, and regulatory authorities in Europe for performing BWR stability analysis. Analysis of many measured BWR stability tests (often performed in European BWRs) provides the basis for the validation for stability parameter calculations (decay ratio and natural frequency) with S3K. This paper summarizes part of the extensive validation database for the code, and discusses the influence of fuel pin model parameters on the stability results.
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Authors
Gerardo Grandi, Lotfi Belblidia, Christian Jönsson,