Examples of advanced fuel cycles for fusion reactors are described. Examples include fuel cycles for use in field reverse configuration (FRC) plasma reactors. In some examples, reaction gases may be removed from a fusion reactor between pulses (e.g. plasmoid collisions). In some examples, a D-.sup.3He reaction is performed, with the .sup.3He provided from decay of byproducts of previous reactions (e.g. tritium).

Examples of advanced fuel cycles for fusion reactors are described. Examples include fuel cycles for use in field reverse configuration (FRC) plasma reactors. In some examples, reaction gases may be removed from a fusion reactor between pulses (e.g. plasmoid collisions). In some examples, a D-.sup.3He reaction is performed, with the .sup.3He provided from decay of byproducts of previous reactions (e.g. tritium).

An apparatus and method for sourcing nuclear fusion products uses an electrochemical loading process to load low-kinetic-energy (low-k) light element particles into a target electrode, which comprises a light-element-absorbing material (e.g., Palladium). An electrolyte solution containing the low-k light element particles is maintained in contact with a backside surface of the target electrode while a bias voltage is applied between the target electrode and an electrochemical anode, thereby causing low-k light element particles to diffuse from the backside surface to an opposing frontside surface of the target electrode. High-kinetic-energy (high-k) light element particles are directed against the frontside, thereby causing fusion reactions each time a high-k light element particle operably collides with a low-k light element particle disposed on the frontside surface. Fusion reaction rates are controlled by adjusting the bias voltage.

New breeder blanket designs and configurations for use in a nuclear fusion reactor to breed Tritium fuel are presented. The breeder blanket designs consist of steel conduits made of different sections, formed of different steels, which are used for the circulation of liquid breeder material.

Electrochemical cells and methods are described that can be utilized for the recovery of tritium directly from a molten lithium metal solution without the need for a separation or concentration step prior to the electrolytic recovery process. The methods and systems utilize an ion conducting electrolyte that conducts either lithium ion or tritide ion across the electrochemical cell.

A system and method for producing tritium are disclosed. The system includes at least one neutron generator configured to generate neutrons. The system further includes at least one target comprising a lithium-containing material. The at least one target is configured to be irradiated by at least some of the neutrons and to produce tritium. The system further includes at least one collection structure configured to receive at least some of the tritium from the at least one target. The at least one collection structure comprises at least one gas conduit having an input configured to receive a carrier gas and an output configured to allow the carrier gas and the received tritium to flow out of the at least one gas conduit after the carrier gas has flowed along the at least one target.

There is provided a quench tank which is disposed in a circulation path of a liquid metal loop and separates and cools liquid metal steam or a mixed gas in liquid metal introduced into a tank body. The tank body includes a separating area which forms a substantially horizontal flow of the liquid metal, and a separating plate is disposed inside the tank body so as to be inclined with respect to the vertical direction.

Certain aspects of the present disclosure are generally directed to tritium shunt heat exchangers that use a sweep gas. In some aspects, a heat exchanger system for a fusion power plant is disclosed herein. The system may advantageously allow for efficient energy and tritium extraction from a tritium-containing fluid, while minimizing tritium leakage into the environment. For example, the system may comprise components, such as a thermally conductive solid connector, a sweep gas, reactive materials, etc., that allow for high heat transfer efficiency, and/or high tritium removal and extraction efficiency. In addition, some aspects of the disclosure are directed to methods for using or making such a system.

A tritium removal device for a lithium loop contains a neutron source (1) for colliding protons on a lithium flow, thereby generating neutrons, a lithium tank (11) for the lithium passing through this neutron source (1) to flow thereto through a flow passage (9), thereby temporarily accumulating it therein, and a lithium pump (17) for circulating and supplying the lithium of this lithium tank (11) to the neutron source (1) through a supply-side flow passage (9). The lithium tank (11) and the lithium pump (17), into which hydrogen gas containing tritium therein can be easily collected, are enclosed within a hermetically sealed container (7) including an inactive gas therein, so that even if the hydrogen gas including the tritium therein is leaked into the hermetically sealed container (7), it is removed by a hydrogen isotope removal filter.

Examples of advanced fuel cycles for fusion reactors are described. Examples include fuel cycles for use in field reverse configuration (FRC) plasma reactors. In some examples, reaction gases may be removed from a fusion reactor between pulses (e.g. plasmoid collisions). In some examples, a D-.sup.3He reaction is performed, with the .sup.3He provided from decay of byproducts of previous reactions (e.g. tritium).