Journals
Publish with us
Publishing partnerships
About us
Blog
Science and Technology of Nuclear Installations
Journal overview
For authors
For reviewers
For editors
Table of Contents
Special Issues
Science and Technology of Nuclear Installations
/
2013
/
Article
/
Fig 3
/
Research Article
Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database
Figure 3
CTF (a) and TRACE (b) predictions of void fraction in bundle type B5 during flow reduction transient.
(a)
(b)