Nuclear reactors

device to initiate and control a sustained nuclear chain reaction

nuclear reactor that uses slow or thermal neutrons

nuclear waste repository excavated deep within a stable geologic environment

nuclear reactors that serve primarily as a neutron source

naturally occurring uranium deposit where self-sustaining nuclear chain reactions have occurred

The Nuclear Engine for Rocket Vehicle Application (NERVA; ) was a nuclear thermal rocket engine development program that ran for roughly two decades. Its principal objective was to "establish a technology base for nuclear rocket engine systems to be utilized in the design and development of propulsion systems for space mission application". It was a joint effort of the Atomic Energy Commission (AEC) and the National Aeronautics and Space Administration (NASA), and was managed by the Space Nuclear Propulsion Office (SNPO) until the program ended in January 1973. SNPO was led by NASA's Harold Fi

thumb|The natural nuclear fission reactors of Oklo:

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atomic electric power plant

pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core

natural nuclear fission reactor discovered in 1972 in the Oklo region of Gabon

nuclear fission reactor concept

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type of nuclear reactor

Russian nuclear fission reactor for use in submarines

nuclear power plant

Soviet nuclear reactor for orbital spacecraft

__NOTOC__ The OPR-1000 is a South Korean-designed two-loop 1000 MWe PWR Generation II nuclear reactor, developed by KHNP and KEPCO. The OPR-1000 was originally designated as the Korean Standard Nuclear Power Plant (KSNP), and was re-designated as the OPR-1000 in 2005 for foreign sales. It was developed based on the Combustion Engineering (C-E)'s system 80 design, through a technology transfer agreement. The reactor core design was derived from the C-E designed Arkansas Nuclear One Unit 2, the nuclear steam supply system (NSSS) was derived from the C-E designed units at Palo Verde Nuclear Gener

Nuclear power system

The RITM-200 is an integrated Generation III+ pressurized water reactor developed by OKBM Afrikantov and designed to produce 55 MWe. The design is an improvement of KLT-40S reactor. It uses up to 20% enriched uranium-235 and can be refueled every 10 years for a 60 year planned lifespan in floating power plant installation. If installed in a stationary power plant, the fuel cycle is 6 years.

US company, 2012 to 2018

nuclear power plant

Russian nuclear pressurized water reactors

type of nuclear reactor

type of nuclear reactor

NRX (National Research Experimental) was a heavy-water-moderated, light-water-cooled, nuclear research reactor at the Canadian Chalk River Laboratories, which came into operation in 1947 at a design power rating of 10 MW (thermal), increasing to 42 MW by 1954. It was Canada's most expensive science facility and the world's most powerful nuclear research reactor at its construction. NRX was remarkable for its heat output and the number of free neutrons it generated. In the late 1940s, the NRX reactor had the highest neutron flux in the world: 10–20 times that of a graphite reactor of comparable

Private company that designs and markets small modular reactors (SMRs)

nuclear reactor design

technical term

device for separating water droplets from steam

Lead-cooled reactor family designed in Russia

building in China Experimental Fast Reactor, China

Nuclear reactor

The BN-reactor is a type of sodium-cooled fast breeder reactor built in Russia from the company OKBM Afrikantov. Two BN-reactors are to date (2015) the only commercial fast breeder reactors in operation worldwide.

nuclear reactor in Halden, Norway

thumbnail|200px|CAREM logo thumb|right|Status of the construction of the CAREM plant in July 2019

nuclear fission reactor

nuclear energy extracted from thorium isotopes

physics branch

The Ultra-High Temperature Reactor Experiment (UHTREX) was an experimental gas-cooled nuclear reactor run at Los Alamos National Laboratory between 1959 and 1971 as part of research into reducing the cost of nuclear power. Its purpose was to test and compare the advantages of using a simple fuel against the disadvantages of a contaminated cooling loop. It first achieved full power in 1969.

alt=MYRRHA Reactor vessel and its internals|thumb|upright=2|MYRRHA Reactor vessel, cutaway view The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a design project of a nuclear reactor coupled to a proton accelerator. This makes it an accelerator-driven system (ADS). MYRRHA will be a lead-bismuth cooled fast reactor with two possible configurations: sub-critical or critical.

nuclear reactor used by the United States Navy

pressurised water reactor series