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International Journal of Nuclear Energy
Table of Contents
International Journal of Nuclear Energy
/
2014
/
Article
/
Fig 11
/
Research Article
Development of Thermal Models and Analysis of UO
2
-BeO Fuel during a Loss of Coolant Accident
Figure 11
Comparison of cladding axial strain at node 7 for MT-1. The dashed line shows case with coolant flux of 1 × 10
−5
kg/m
2
s.