RECYCLING OF PLUTONIUM ON MOLTEN SALT REACTOR TYPE FUJI-U3
Molten Salt Reactor (MSR) has been selected as one of the Generation IV nuclear power system that was developed in Japan. The fuel salt is composed of 71.76% LiF, 16% BeF2, 12% ThF4 dan 0.24% 233UF4, and graphite as moderator. Specifically, we focused on Fuji-U3 design which is originally consider 2...
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| المؤلف الرئيسي: | |
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| التنسيق: | Theses |
| اللغة: | Indonesia |
| الوصول للمادة أونلاين: | https://digilib.itb.ac.id/gdl/view/21521 |
| الوسوم: |
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