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1. 发明申请

WO2021170157A1 DEVICE FOR RECOVERY OF ENERGY FROM SPENT FUEL OF NUCLEAR REACTORS AND PROCESS FOR ENERGY RECOVERY FROM SPENT FUEL OF NUCLEAR REACTORS 审中-公开
公开(公告)号：WO2021170157A1
公开(公告)日：2021-09-02
申请号：PCT/CZ2021/050020
申请日：2021-02-17
申请人： SKODA, Radek
发明人： SKODA, Radek
IPC分类号： G21C1/06 , G21C5/12 , G21C19/48
摘要： Due to the parasitic absorption of neutrons on fission debris, in VVER-, BWR-, and PWR-type nuclear reactors, fuel is nowadays removed from the reactor, although the fuel still contains some usable material. This material is further utilized with the release of energy in the device described in the invention. In the device for recovery of energy from spent fuel of nuclear reactors, already irradiated fuel assemblies are used in other geometries, using different physical parameters and materials than in the original reactors. In particular, the fuel is operated at maximum fuel temperature lower than in the reactor in which it was originally irradiated, at a temperature at least 150 C lower than in the case of fuel from a VVER reactor, 160 C lower than in the case of fuel from a BWR reactor, and 140 C lower than in the case of fuel from a PWR reactor. The moderator in this device has lower absorption in the fuel than in the reactor in which it was originally irradiated, at least 5% lower in the case of fuel from a VVER reactor, at least 5% lower in the case of fuel from a BWR reactor, and at least 7% lower in the case of spent fuel of a PWR reactor. The coolant of the device for recovery of energy from spent fuel of VVER nuclear reactors is at a pressure lower than 12 MPa, in the case of spent fuel of BWR reactors, it is at a pressure lower than 6.5 MPa, and in the case of spent fuel of PWR reactors, it is at a pressure lower than 15 MPa. The spacing between the centers of some of the fuel assemblies of the device for recovery of energy from spent fuel of nuclear reactors is larger than in the reactor in which the fuel was originally irradiated, 3 mm larger in the case of fuel from a VVER reactor, 2 mm larger in the case of fuel from a BWR reactor, and 3 mm larger in the case of fuel from a PWR reactor. The device for recovery of energy from spent fuel of nuclear reactors is primarily designed for the heating industry and can be used also with non-irradiated fuel.

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