24 relations: Brayton cycle, Energy Multiplier Module, Fast-neutron reactor, Framatome, Fuji Electric, Gas-cooled fast reactor, General Atomics, Graphite, Helium, Kurchatov Institute, Light-water reactor, Neutron moderator, Neutron temperature, Nuclear fission, Nuclear fuel, Nuclear reactor, Nuclear reactor core, Nuclear transmutation, OKBM Afrikantov, Pebble-bed reactor, Prism (geometry), Radioactive waste, Rankine cycle, Very-high-temperature reactor.
The Brayton cycle is a thermodynamic cycle named after George Brayton who describes the workings of a constant-pressure heat engine.
The Energy Multiplier Module (EM2 or EM squared) is a nuclear fission power reactor under development by General Atomics.
A fast-neutron reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons, as opposed to thermal neutrons used in thermal-neutron reactors.
Framatome is a French reactor business.
, operating under the brand name FE, is a Japanese electrical equipment company, manufacturing pressure transmitters, flowmeters, gas analyzers, controllers, inverters, pumps, generators, ICs, motors, and power equipment.
The gas-cooled fast reactor (GFR) system is a nuclear reactor design which is currently in development.
General Atomics is a defense contractor headquartered in San Diego, California, specializing in nuclear physics including nuclear fission and nuclear fusion.
Graphite, archaically referred to as plumbago, is a crystalline allotrope of carbon, a semimetal, a native element mineral, and a form of coal.
Helium (from lit) is a chemical element with symbol He and atomic number 2.
The Kurchatov Institute (Hациональный исследовательский центр "Курчатовский Институт" (since 2010) i.e. (Russia's) National Research Centre "Kurchatov Institute"; 1991-2010: Роcсийский научный центр "Курчатовский Институт". — Russian Scientific Centre "Kurchatov Institute") is Russia's leading research and development institution in the field of nuclear energy.
The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator – furthermore a solid form of fissile elements is used as fuel.
In nuclear engineering, a neutron moderator is a medium that reduces the speed of fast neutrons, thereby turning them into thermal neutrons capable of sustaining a nuclear chain reaction involving uranium-235 or a similar fissile nuclide.
The neutron detection temperature, also called the neutron energy, indicates a free neutron's kinetic energy, usually given in electron volts.
In nuclear physics and nuclear chemistry, nuclear fission is either a nuclear reaction or a radioactive decay process in which the nucleus of an atom splits into smaller parts (lighter nuclei).
Nuclear fuel is a substance that is used in nuclear power stations to produce heat to power turbines.
A nuclear reactor, formerly known as an atomic pile, is a device used to initiate and control a self-sustained nuclear chain reaction.
A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat is generated.
Nuclear transmutation is the conversion of one chemical element or an isotope into another chemical element.
OKBM Afrikantov (full name: OAO I. I. Afrikantov OKB Mechanical Engineering, Опытное конструкторское бюро машиностроения им.) is a nuclear engineering company located in Nizhny Novgorod, Russia.
The pebble-bed reactor (PBR) is a design for a graphite-moderated, gas-cooled nuclear reactor.
In geometry, a prism is a polyhedron comprising an n-sided polygonal base, a second base which is a translated copy (rigidly moved without rotation) of the first, and n other faces (necessarily all parallelograms) joining corresponding sides of the two bases.
Radioactive waste is waste that contains radioactive material.
The Rankine cycle is a model used to predict the performance of steam turbine systems.
The very-high-temperature reactor (VHTR), or high-temperature gas-cooled reactor (HTGR), is a Generation IV reactor concept that uses a graphite-moderated nuclear reactor with a once-through uranium fuel cycle.