Reliability Assessment of 2400 MWth Gas-Cooled Fast Reactor Natural Circulation Decay Heat Removal in Pressurized Situations

<table>Development
of the deductive approach for critical parameters determination
(NCDHR pressure drops “1”).</table>

Science and Technology of Nuclear Installations

Figure 9: Reliability Assessment of 2400 MWth Gas-Cooled Fast Reactor Natural Circulation Decay Heat Removal in Pressurized Situations 