Method of operating a nuclear power plant

    公开(公告)号:US11875906B2

    公开(公告)日:2024-01-16

    申请号:US17950830

    申请日:2022-09-22

    Inventor: David Leblanc

    Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.

    Method for the construction of a secure nuclear reactor plant, and corresponding reactor plant

    公开(公告)号:US09812227B2

    公开(公告)日:2017-11-07

    申请号:US14130360

    申请日:2012-07-02

    CPC classification number: G21D1/00 G21F7/00 Y02E30/40

    Abstract: Disclosed is a method for building a nuclear reactor installation including a containment chamber surrounded by a protective casing. The method is characterised by the following essential construction phases: finding or preparing a cavern (2) in rocky ground or a mountain (3) which is connected to the outside world via a tunnel or shaft (4), constructing or introducing a sealed protective casing (5) made of steel which delimits the containment chamber (1) forming an enveloping intermediate chamber volume (6) between the protective casing (5) and the cavern walls (2′), and, filling the intermediate chamber (6) with concrete or cement (6′), with the exception of the tunnel or shaft (4).

    SYSTEMS AND METHODS FOR THERMAL INTERCONNECT

    公开(公告)号:US20170294240A1

    公开(公告)日:2017-10-12

    申请号:US15357875

    申请日:2016-11-21

    CPC classification number: G21C1/22 G21C3/54 G21C15/02 G21D1/00 G21D3/04 Y02E30/38

    Abstract: A power system can connect to a nuclear reactor through a standardized connection. The standardized connection is configured so that the nuclear reactor may be designed independently of the power system. Systems include a reactor core in fluid communication with a heat exchanger. A fluid loop passes through the heat exchanger. The system includes an output and inlet manifolds at the ends of the fluid loop, terminating in ports that include a standardized connection mechanism. When the secondary system is coupled to the connection mechanism, the fluid loop and the secondary system define a distal loop. A working fluid can then flow through the distal loop and transfer heat from the reactor core to the secondary system.

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