Article ID Journal Published Year Pages File Type
5475094 Annals of Nuclear Energy 2017 8 Pages PDF
Abstract
In this paper we compare the performance of the CHD code with other similar fast reactor dynamics codes using a benchmark study of the European Sodium cooled Fast Reactor (ESFR). The results agree well, both qualitatively and quantitatively with the code benchmark. In addition, we demonstrate the code's ability to simulate the long-term asymptotic behavior of a neutronically shut down reactor in an unprotected loss of flow scenario using a model of the Advanced Burner Reactor (ABR).
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Authors
, ,