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Fast Breeder Reactor

A Fast Breeder Reactor is a reactor that uses fast neutron, and generates more nuclear fuels(plutonium 239) than that consumed when generating power to enhance dramatically the efficiency of the use of resources. Nuclear fission by fast neutron causes the increase in neutrons generated. Furthermore, because the sodium coolant absorbs fewer neutrons as compared to light water reactor, more neutrons remain within the reactor. Increased number of neutrons causes higher proportion of plutonium 239 converted from uranium 238 and yields more plutonium than original nuclear fuel.
In Japan, an experimental fast-breeder reactor "Joyo" was first developed by the Japan Atomic Energy Agency(JAEA)(former Power Reactor & Nuclear Fuel Development Corporation). This is a reactor without electric generating facilities, and started operation in 1977 with the aim of accumulating technical experience on the fast-breeder reactor.
MHI was in charge of the design of the core and the manufacture of the rotary plugs, intermediate heat exchangers and secondary coolant system. Furthermore, MHI actively participated in the Mk-III(3) modification works that increased the output of 50 MW to 100 MW then to 140 MW.

Following "Joyo", a prototype fast-breeder "Monju" was developed as a national project. The objective of this project was, through experience of design, construction and operation, to verify technically the performance and reliability of power plant, as well as to establish sodium handling technologies. After the sodium leak accident on the secondary cooling system in December 1995, operation of the facility had been stopped. But, learning lessons from the accident, the modification works have been started in September 2005, after comprehensive checking of the whole facilities. MHI also cooperates fully for the restart of the reactor.
1970 Start construction of Experimental reactor "Joyo"
1977 Initial criticality of "Joyo"
1985 Start construction of Prototype reactor "Monju"
1994 Initial criticality of "Monju"
1995 "Monju" sodium leak accident
Installation of Monju reactor vessel at site Steam generator of Monju -Evaporator tube bundle block-
Core intemals of Monju -Core support plate and connecting pipes-
Monju

Business contact: Nuclear Energy Systems Nuclear Energy Systems Administration Department Planning Group +81-3-6716-4812

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