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Nuclear energy will move to a “fast” future, to the closure of the nuclear fuel cycle, using nitride fuel. Mixed nitride uranium-plutonium (MNUP) fuel is a type of nuclear fuel in which the fissile material (a mixture of uranium and plutonium) is presented in the form of a nitrogen compound, mononitride, instead of the standard uranium dioxide. This fuel is not yet used in industry; it is being developed for advanced fast neutron reactors with sodium and lead coolants. Boris Martsinkevich will tell you more about SNUP fuel.
0:00 SNUP fuel and its advantages over conventional fuel
1:27 Problems of using SNUP fuel in conventional reactors
2:57 Advantages of using SNUP fuel in fast neutron reactors
5:10 Safety considerations for SNUP fuel
7:40 Use of lead as a coolant in fast neutron reactors
9:50 Plutonium storage in Russia
12:20 The role of the Mayak enterprise in Russia
13:40 Development of the BREST-300 reactor
16:20 Differences in the use of SNUP fuel and MOX fuel
19:50 The future of fast neutron reactors
23:30 Safety of fast neutron reactors
24:50 Problems and advantages of using SNUP fuel
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