Nuclear reactors have very few systems for significantly reduced failure possibilities. Nuclear reactors may be boiling water reactors with natural circulation-enabling heights and smaller, flexible energy outputs in the 0-350 megawatt-electric range. Reactors are fully surrounded by an impermeable, high-pressure containment. No coolant pools, heat sinks, active pumps, or other emergency fluid sources may be present inside containment; emergency cooling, like isolation condenser systems, are outside containment. Isolation valves integral with the reactor pressure vessel provide working and emergency fluid through containment to the reactor. Isolation valves are one-piece, welded, or otherwise integral with reactors and fluid conduits having ASME-compliance to eliminate risk of shear failure. Containment may be completely underground and seismically insulated to minimize footprint and above-ground target area.

A reactor water radioactivity concentration of a nuclear power plant can be predicted with high accuracy. First, a plant state quantity prediction value is calculated by using a physical model that describes plant state quantities of the power plant including a flow rate of feedwater and a metal corrosion product concentration in feedwater of the reactor water is calculated. Next, data for supervised learning is created, and the data for supervised learning includes the previously calculated plant state quantity prediction value and a plant state quantity such as the flow rate of feedwater, the metal corrosion product concentration in feedwater, a metal corrosion product concentration in reactor water, and a radioactive metal corrosion concentration of the reactor water in the reactor as input data and includes a radioactive metal corrosion concentration in the reactor water which is an actual measured value as output data, and a predictive model is trained.

An introduction of nuclear fusion into conventionally fission-based nuclear reactors. Particularly, coolant in the reactor serves as the secondary fuel that absorbs neutrons from the fission core, and releases energy through fusion reactions. Molten Lithium is the preferred coolant in the invention, as it produces Helium gas through the neutron-Lithium fusion without leaving any radioactive or chemical impact to the environment. A Helium pressure controller is also introduced in the system to manage the Helium gas produced by nuclear reactions of the secondary fuel. Lithium Chloride (LiCl) is proposed as the secondary coolant in lieu of the commonly used molten salt in order to achieve higher power production efficiency. A reactor based on the proposed system requires less space than a conventional reactor of the same power. It is a better choice than conventional nuclear reactors when space is a key constraint, for example, on a container ship.

The present invention relates to a molten salt-metal reactor for implementing a micro-reactor, and more specifically, to a molten salt-metal reactor including a liquid metal nuclear fuel and a molten salt coolant, wherein the molten salt coolant is disposed in an upper portion of the liquid metal nuclear fuel such that the heat generated from the nuclear fuel is transferred to the molten salt coolant and cooled.

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 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.

A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.

A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.

The invention belongs to the technical field of nuclear reactor materials design, and discloses a method for improving the withstanding capability of the cladding material in the fast neutron irradiation environment, comprising the following steps: selecting the cladding material with the annular structure and placing it on the outer side of the metallic fuel slug, with leaving a 0.2-0.8 mm gap between the metallic fuel slug and the cladding material; processing the operation in a reactor subsequently, with an annealing process of the fast neutron reactor fuel during the operation of the reactor; improves the withstanding capability of the cladding material in the fast neutron irradiation environment. The invention processes annealing treatment of the cladding material by balancing the internal and external stresses, multiple cycles of steady-state and transient operations, enhancing the withstanding capability of the steel in the high neutron irradiation environment, improving the lifetime of the cladding material.