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Neutron Flux is a measure of the number of neutrons passing through a unit area per second, important in fusion reactions because neutrons carry away much of the energy. Managing neutron flux is necessary for material integrity and energy capture in a fusion reactor.

A divertor is a component of magnetic confinement fusion reactors, particularly tokamaks, which removes waste heat and particles from the plasma, maintaining purity and protecting the reactor's walls. Developing durable and efficient divertors is crucial for long-term operation of fusion reactors.

A tokamak is a device utilizing magnetic fields to confine a plasma in a toroidal shape. It is the leading candidate for achieving controlled nuclear fusion, with ITER being the largest and most advanced tokamak project.

Triple product refers to the product of plasma density, temperature, and confinement time. It is a key parameter in evaluating the performance of a fusion reactor and must exceed a certain threshold (Lawson Criterion) for net energy gain.

Nuclear fusion involves combining light nuclei to form heavier ones, releasing energy, while fission splits heavy nuclei into lighter ones, also releasing energy. Fusion research is motivated by its potential for cleaner, safer, and virtually limitless energy compared to fission.

The Lawson Criterion provides conditions for net energy gain from fusion, requiring a product of plasma density, confinement time, and temperature. Research efforts aim to meet or exceed these criteria in experimental reactors.

The Fusion Energy Gain Factor, Q, measures the ratio of fusion power produced to the power required to maintain the plasma. A Q value greater than 1 (Q>1) is necessary for a practical fusion power plant, and current research is working towards achieving a Q>1.

Cryogenic fuel pellets contain deuterium and tritium and are used as fuel in inertial confinement fusion. These pellets must be kept at extremely low temperatures before being rapidly compressed and heated to initiate fusion. Current research is investigating pellet designs for optimal compression and ignition.

The fusion cross section is a measure of the probability of fusion reactions occurring between the nuclei in a plasma, often maximized at certain energies. Research in fusion aims to maximize the fusion cross section through temperature and plasma condition control.

Fusion ignition is the point at which a fusion reaction becomes self-sustaining, generating enough heat to sustain further reactions without continuous external input. Research aims to reach this milestone to achieve a net energy positive fusion reactor.

Magnetic Confinement Fusion uses strong magnetic fields to confine and control the plasma needed for fusion. Tokamaks and stellarators are examples of MCF devices under intense research to solve the fusion puzzle.

Thermonuclear fusion is the process of fusing atomic nuclei under extremely high temperatures, akin to the processes within stars. The primary challenge and focus of fusion research is to replicate these conditions on Earth in a controlled manner.

Magnetic Mirrors are a type of magnetic confinement device that use magnetic fields to confine plasma in a linear configuration. The concept has seen less focus compared to tokamaks and stellarators but is still under study for potential applications.

Deuterium-Tritium fusion is the most studied fusion reaction because it has the highest energy yield at the lowest temperatures. Currently, research focuses on achieving and maintaining the conditions necessary for D-T fusion in devices like tokamaks and inertial confinement fusion facilities.

Aneutronic fusion is a type of nuclear fusion reaction that releases little to no neutrons, typically involving fuel cycles like hydrogen-boron. While theoretically advantageous due to reduced radiation, it requires much higher temperatures and is currently less practical.

Bremsstrahlung is a type of radiation loss where a charged particle decelerates near another charged particle, causing energy loss in the form of photons. Minimizing Bremsstrahlung losses is important for achieving net energy gain in fusion reactors, especially for electron-rich plasmas.

Quantum Electrodynamics (QED) plasma effects include phenomena that occur due to quantum corrections in the behavior of plasmas. Such effects are typically negligible but may become significant at the very high fields and densities contemplated for advanced fusion concepts.

Fusion reactor materials must withstand extreme temperatures, radiation (especially neutrons), and mechanical stress. Research into materials science focuses on discovering and engineering materials capable of enduring the harsh environment inside a fusion reactor over its lifetime.

Inertial Confinement Fusion involves compressing and heating small fuel pellets with lasers or ion beams until fusion occurs. Research is ongoing, notably at the National Ignition Facility (NIF), to reach the ignition point where fusion becomes self-sustaining.

Cyclotron radiation is the electromagnetic radiation emitted by charged particles spiraling along magnetic field lines. In nuclear fusion reactors, it is crucial to minimize these losses for high-Z ions to maintain plasma temperature.

Tritium breeding refers to the process of generating tritium, a key fuel for D-T fusion, within a reactor through neutron interactions with lithium. Research is focused on developing reliable and safe tritium breeding methods, as tritium is scarce and not naturally abundant.

Ignition temperature is the minimum temperature at which the fuel mixture (usually D-T) will undergo self-sustaining fusion reactions without external energy input. It is dependent on pressure and fuel composition, and research is directed towards achieving these temperatures in a controlled setting.

In inertial confinement fusion, direct drive refers to the application of laser energy directly onto the fuel pellet, whereas indirect drive uses a surrounding container to convert laser energy into x-rays that compress the pellet. Both methods are being researched for effective pellet ignition.

A blanket module in fusion reactors surrounds the core and serves to absorb neutrons, generate tritium (in D-T reactors), and transfer heat for power production. Research is ongoing to develop blanket materials and technologies that can efficiently perform these roles.

The stellarator is an alternative to the tokamak for magnetic confinement of plasma in nuclear fusion research. Stellarators aim for steady state operation and have complex twisted magnetic coils, with Wendelstein 7-X being a prominent example.

Alpha heating occurs when alpha particles (helium nuclei) produced by D-T fusion reactions transfer their kinetic energy to the plasma, potentially contributing to the plasma heating process. Research efforts aim to use alpha heating to achieve ignition and a self-sustaining fusion reaction.

MHD instabilities occur when the plasma's magnetic fields and fluid properties interact to destabilize the confinement. These instabilities present challenges for maintaining a stable fusion process, with research dedicated to understanding and controlling MHD phenomena.

Plasma confinement involves containing a high-temperature plasma so that fusion can occur. Magnetic confinement in tokamaks and inertial confinement with lasers are the primary methods under research for achieving sustained fusion reactions.

Energy confinement time is the average time that energy is retained within the plasma before being lost. Achieving a longer confinement time is a significant challenge in fusion research, critical for obtaining net energy output.