The present invention relates to a device adapted for producing energy by nuclear fission, the device comprising a core container of a core container material, which core container encloses an inner tubing of an inner tubing material, the inner tubing and/or the core container having an inlet and an outlet, the device further comprising a molten halide salt located in the core container or in the inner tubing, wherein the inner tubing comprises one or more sections consisting of single crystal corundum. The invention further relates to methods of controlling nuclear fission processes using the device and to the use of a corundum tube as a structural material in a nuclear fission device. The invention provides improved economy in molten salt nuclear fission processes.

The present invention relates to a device adapted for producing energy by nuclear fission, the device comprising a core container of a core container material, which core container encloses an inner tubing of an inner tubing material, the inner tubing and/or the core container having an inlet and an outlet, the device further comprising a molten halide salt located in the core container or in the inner tubing, wherein the inner tubing comprises one or more sections consisting of single crystal corundum. The invention further relates to methods of controlling nuclear fission processes using the device and to the use of a corundum tube as a structural material in a nuclear fission device. The invention provides improved economy in molten salt nuclear fission processes.

A power generation system includes an inert gas power source, a thermal/electrical power converter and a power plant. The thermal/electrical power converter includes a compressor with an output coupled to an input of the inert gas power source. The power plant has an input coupled in series with an output of the thermal/electrical power converter. The thermal/electrical power converter and the power plant are configured to serially convert thermal power produced at an output of the inert gas power source into electricity. The thermal/electrical power converter includes an inert gas reservoir tank coupled to an input of the compressor via a reservoir tank control valve and to the output of the compressor via another reservoir tank control valve. The reservoir tank control valve and the another reservoir tank control valve are configured to regulate a temperature of the output of the thermal/electrical power converter.

The invention relates to a nuclear reactor operating according to the dual fluid principle with a special liquid metal fissionable mixture as liquid fuel in the liquid fuel line, which has a high percentage of actinoids, preferably 69% and higher. Preferred metals are selected from chromium (Cr), manganese (Mn) and iron (Fe). Preferred actinoids are selected from thorium (Th), uranium (U) and plutonium (Pu). The mixtures and resulting multicomponent alloys need not necessarily be an eutectic.

The invention relates to the technical field of nuclear reactor materials, in particular to a processing method for improving the corrosion resistance of iron and steel materials in lead or lead-bismuth, comprising the following steps: selecting iron and steel materials containing Mn and Cr elements, using high-energy fast neutrons generated by fission as the radiation source, and performing irradiation on the iron and steel material so that Mn and Cr elements diffuse to the surface of the iron and steel material to form a dense oxide film, so as to complete the improvement of the corrosion resistance of the iron and steel material. The invention enhances the formation of the dense-structured oxide layer by irradiation. The oxide layer has good protection and self-healing properties in irradiation environment, and a new solution is proposed for enhancing the corrosion resistance of steel in lead and lead-bismuth coolant fast reactors.

The invention relates to the technical field of nuclear reactor materials, in particular to a processing method for improving the corrosion resistance of iron and steel materials in lead or lead-bismuth, comprising the following steps: selecting iron and steel materials containing Mn and Cr elements, using high-energy fast neutrons generated by fission as the radiation source, and performing irradiation on the iron and steel material so that Mn and Cr elements diffuse to the surface of the iron and steel material to form a dense oxide film, so as to complete the improvement of the corrosion resistance of the iron and steel material. The invention enhances the formation of the dense-structured oxide layer by irradiation. The oxide layer has good protection and self-healing properties in irradiation environment, and a new solution is proposed for enhancing the corrosion resistance of steel in lead and lead-bismuth coolant fast reactors.

A molten fuel salt nuclear reactor core assembly including a fluid neutron reflecting material defining a fast spectrum fuel volume configured to breed fissile fuel from fertile fuel, a first inlet channel, and a first outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the fast spectrum fuel volume. The core assembly also includes a set of neutron absorbing members sized to fit within the fast spectrum fuel volume. The set of neutron absorbing members define a thermal spectrum fuel volume for a fission reaction of the fissile fuel, a second inlet channel, and a second outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the thermal spectrum fuel volume.

An energy source using low-enriched nuclear fuel to produce heat contains a compact transportable pressure vessel containing a cylinder with the core with heating element formed by nuclear fuel and continually agitated by a directed flow of heat-exchange liquid, to which a second pressure vessel is connected with a closed water bath circuit and a heat exchanger for production of steam, while the compact transportable pressure vessel can be placed in a space selected from the group underground concrete space with stainless steel lining, sea-river vessel and container modification for road and/or railway transport.

An energy source using low-enriched nuclear fuel to produce heat contains a compact transportable pressure vessel containing a cylinder with the core with heating element formed by nuclear fuel and continually agitated by a directed flow of heat-exchange liquid, to which a second pressure vessel is connected with a closed water bath circuit and a heat exchanger for production of steam, while the compact transportable pressure vessel can be placed in a space selected from the group underground concrete space with stainless steel lining, sea-river vessel and container modification for road and/or railway transport.

A multipurpose passive residual heat removal system for a small fluoride-salt-cooled high-temperature reactor is provided, including: a circulation loop composed of a reactor body system, a multipurpose passive residual heat removal system, pipes and other connecting equipment between each system; wherein the reactor body system serves as the heat source of the system, using helical cruciform fuel element and FLiBe molten salt coolant, wherein a thermal power is 125 MW, and a temperature of the core outlet reaches 700° C., which has the advantages of high-temperature and low-pressure operation, inherent safety and compact structure. The multipurpose passive residual heat removal system not only serves as a special safety facility to ensure the passive safety of the reactor, but also efficiently recovers and utilizes the residual heat through the thermoelectric power generation device for power generation.