Intermediate neutron reactor - a nuclear reactor that uses neutrons with an energy of 0.025 - 1000 eV to maintain a nuclear chain reaction .
The concentration of fissile materials in the reactor core at intermediate neutrons is such that fast neutrons are slowed down to an energy of 1-1000 eV before absorption. For example, the ratio of beryllium nuclei to 235 U in such reactors ranges from 150 to 250.
Intermediate neutron power reactors are used relatively rarely for two reasons. These reactors require a high degree of nuclear fuel enrichment compared to thermal neutron reactors . Secondly, in the core of such a reactor, no more than 1.5-2.0 neutrons are emitted per neutron capture. Therefore, in intermediate neutron reactors it is impossible to carry out expanded reproduction of nuclear fuel, as in a fast neutron breeder reactor.
Intermediate neutron reactors are used as research reactors, since they manage to obtain a very high neutron flux density. For example, the maximum neutron flux density in the SM-2 reactor built in the USSR is 3.3 × 10 19 neutrons / (m 2 · s).
However, on some submarine projects of the USSR, intermediate neutron reactors with liquid metal coolant were installed, which proved to be good.
Literature
- Levin V.E. Nuclear physics and nuclear reactors. 4th ed. - M .: Atomizdat , 1979.
- Petunin V.P. Thermal energy of nuclear installations M .: Atomizdat , 1960.