System for transmuting nuclear wastes by utilizing isotopic neutron source

[0016] The present invention will be further described below in conjunction with the drawings and specific embodiments.

[0017] Such as figure 1 As shown, the present invention includes: a nuclear waste assembly 1, a neutron source assembly 2, a liquid medium 3, a heat exchanger 4, a graphite reflective layer 5, a concrete shielding layer 6 and a refueling mechanism 7. The neutron source component 2 uses high-yield isotope neutron sources, such as Cf-252 neutron sources. Of course, waste isotope neutron sources such as medical and scientific research can also be used to achieve the purpose of making full use of resources. In order to ensure full utilization of the isotope neutron source, the neutron source assembly 2 is made into a cylindrical shape with a long line. The nuclear waste component 1 is made of MA. In order to ensure a sufficient reaction, the nuclear waste component 1 is also made into a long cylindrical shape. The selection of liquid metal for the liquid medium 3 mainly considers two reasons: First, the liquid metal can effectively derive the heat generated by the transmutation reaction and the heat generated by the decay of nuclear waste. In addition, the use of liquid metal as a coolant is conducive to maintaining the speed of fast neutrons, so that MA has a larger fission section and increases the transmutation performance of the system.

[0018] Such as figure 2 As shown, the nuclear waste component 1 and the neutron source component 2 are evenly arranged in a uniformly spaced manner, the nuclear waste component 1 and the neutron source component 2 are arranged in sequence, and any adjacent three components are distributed in a triangular shape. The spacing is selected according to the actual situation to ensure that the system is in a subcritical state.

[0019] Since the nuclear waste component 1 generates heat during the decay process and the transmutation process also generates heat, it is necessary to export heat from the system. The heat exchanger 4 is cooled in the liquid medium 3 to maintain the liquid medium 3 at the required temperature. The graphite reflective layer 5 mainly prevents neutron leakage and at the same time plays a certain shielding role. The entire reaction process has a certain amount of radioactivity, and a shielding layer needs to be provided. The concrete shielding layer 6 plays a shielding role for the entire system. When the reaction progresses to a certain extent, for example, the nuclear waste component 1 has been completely transmuted, and the radioactivity is lower than a certain requirement. At this time, a new nuclear waste component 1 needs to be replaced by the refueling mechanism 7. Or the isotope neutron source assembly 2 has already decayed, and a new neutron source is needed at this time, and the new neutron source assembly 2 is replaced through the refueling mechanism 7, and the refueling mechanism 7 can move freely in the system.

[0020] Although the illustrative specific embodiments of the present invention have been described above to facilitate those skilled in the art to understand the present invention, it should be clear that the present invention is not limited to the scope of the specific embodiments. For those of ordinary skill in the art, As long as the various changes are within the spirit and scope of the present invention defined and determined by the appended claims, these changes are obvious, and all inventions and creations using the concept of the present invention are protected.