The steam generating unit of dual circuit reactor with blowdown and drain system is implemented in the close loop, without any conventional blowdown expansion tanks and is designed for maximum pressure of the steam generator (SG) working medium. The SG blowdown water is combined into a single line, cooled down in the regenerative heat exchanger, then in the blowdown aftercooler and drain cooling line and taken out of the tight shell. Out of the tight shell, the SG blowdown water is supplied for treatment to the SG blowdown water treatment system designed for maximum pressure of the steam generator (SG) working medium. After treatment, the water returns to the tight shell and, via the regenerative heat exchanger, to the feed pipelines of each SG. The invention provides increased SG blowdown that leads to the accelerated chemical condition normalization even with considerable deviations.

The steam generating unit of dual circuit reactor with blowdown and drain system is implemented in the close loop, without any conventional blowdown expansion tanks and is designed for maximum pressure of the steam generator (SG) working medium. The SG blowdown water is combined into a single line, cooled down in the regenerative heat exchanger, then in the blowdown aftercooler and drain cooling line and taken out of the tight shell. Out of the tight shell, the SG blowdown water is supplied for treatment to the SG blowdown water treatment system designed for maximum pressure of the steam generator (SG) working medium. After treatment, the water returns to the tight shell and, via the regenerative heat exchanger, to the feed pipelines of each SG. The invention provides increased SG blowdown that leads to the accelerated chemical condition normalization even with considerable deviations.

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.

A method for depositing zinc on the surfaces of a coolant loop of a nuclear power plant includes: providing within a portion of the coolant loop a treatment solution comprising zinc and optionally one or more noble metals and/or reducing agent(s); allowing the treatment solution to remain in the portion for a treatment period; and removing the treatment solution from the portion. According to various embodiments, an average temperature of the treatment solution over the course of the treatment period is less than 150° C. or 100° C. According to various embodiments, an instantaneous temperature of the treatment solution remains below 150° C. or 100° C. throughout the treatment period. The zinc deposition treatment may be applied (1) before the plant is first put into power-generating operation or (2) during an outage following power-generating operation and optionally following a chemical decontamination to remove any oxides formed on surfaces of a coolant loop during prior power operation period(s).

A method for depositing zinc on the surfaces of a coolant loop of a nuclear power plant includes: providing within a portion of the coolant loop a treatment solution comprising zinc and optionally one or more noble metals and/or reducing agent(s); allowing the treatment solution to remain in the portion for a treatment period; and removing the treatment solution from the portion. According to various embodiments, an average temperature of the treatment solution over the course of the treatment period is less than 150° C. or 100° C. According to various embodiments, an instantaneous temperature of the treatment solution remains below 150° C. or 100° C. throughout the treatment period. The zinc deposition treatment may be applied (1) before the plant is first put into power-generating operation or (2) during an outage following power-generating operation and optionally following a chemical decontamination to remove any oxides formed on surfaces of a coolant loop during prior power operation period(s).

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.

A flow control device configured to be positioned in a reactor core. The flow control device including a central shaft and at least one blade extending helically from the central shaft. A nuclear reactor and related systems and methods are also disclosed.

A flow control device configured to be positioned in a reactor core. The flow control device including a central shaft and at least one blade extending helically from the central shaft. A nuclear reactor and related systems and methods are also disclosed.

The patent discloses method and control system for gas injection into the coolant of a nuclear reactor plant. The method includes the following steps: gas to be injected into the coolant is supplied from the gas system to the above-coolant space; gas is injected into the gas system from the above-coolant space. Technical result: prevention of reuse of contaminated gas.

This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UCl.sub.xF.sub.y are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.