| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 10139096 | Nuclear Engineering and Design | 2018 | 10 Pages |
Abstract
- Benchmark on sodium-cooled fast reactor, ASTRID-like core.
- NRG SPECTRA code simulation of the ASTRID ULOF scenario.
- Effect of dynamic gap expansion on ASTRID-like core temperatures during ULOF.
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
M.M. Stempniewicz, E.A.R. de Geus, F. Roelofs,