Study of some important aspects of inherent safety of BREST-300, generation IV lead-cooled fast reactor
A Russian design of Lead- cooled Fast Reactor (LFR) with a mixed uranium-plutonium nitride fuel is chosen as a case study. In order to demonstrate the inherent safety considered in this proposed design in the framework of Generation IV of nuclear reactors, a precise simulation of core has been attem...
| Main Authors: | , , |
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| Format: | Article |
| Language: | fas |
| Published: |
Nuclear Science and Technology Research Institute
2015-05-01
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| Series: | مجله علوم و فنون هستهای |
| Subjects: | |
| Online Access: | https://jonsat.nstri.ir/article_69_23e4a93ca806f6fc4088bfb2e1edaf4a.pdf |