The S1G reactor is a United States Naval reactor constructed by General Electric as a prototype for the USS Seawolf (SSN-575) submarine. It is a liquid metal reactor using pure sodium to cool the core instead of water. It had problems because of the limited room in operating temperature. ...more on Wikipedia about "S1G reactor"
The S1W nuclear reactor was a Westinghouse Electric Corporation-built naval reactor. The designation "S1W" can be translated as follows: ...more on Wikipedia about "S1W reactor"
The S3G reactor is a type of United States Naval reactor, used to drive a submarine. ...more on Wikipedia about "S3G reactor"
The S5G nuclear reactor, the fifth submarine reactor designed by General Electric, was installed as a land based prototype at the Nuclear Power Training Unit, Idaho National Engineering Laboratory near Idaho Falls, Idaho and on Narwhal (SSN-671). It was intended to test the potential contribution of natural circulation technology to submarine quieting. Reactor primary coolant pumps are one of the primary sources of noise from submarines, and the elimination of coolant pumps and associated equipment would also reduce mechanical complexity and the volume required by propulsion equipment. Its design was the direct ancestor of the S8G reactor used in the Ohio-class submarines. ...more on Wikipedia about "S5G reactor"
The Westinghouse Electric Corporation's S5W nuclear reactor is a pressurized-water nuclear fission reactor intended to power submarines. This type's simplicity, overdesign, and redundancy was intended for ease of operation and to tolerate battle damage; these characteristics contributed greatly to the type's reliability, longevity, and sterling safety record. S5W was the standard reactor for submarines of the United States Navy from its first use in 1959 on USS Skipjack (SSN-585) until the introduction of the Los Angeles class submarines in the mid- 1970s. One such plant was also used in Britain's first nuclear-powered submarine HMS Dreadnought (S101). As of 2005, two S5W reactor plants remain in service, ex-USS Daniel Webster (MTS-626) and ex-USS Sam Rayburn (MTS-635). These plants are used to train naval nuclear operators; the designation MTS stands for "moored training ship." ...more on Wikipedia about "S5W reactor"
The S6G reactor plant consists of the reactor coolant, steam generating and other support systems that supplies steam to the engine room of United States Navy's Los Angeles-class submarines. The 688-class engine room powers two steam turbines that propel a single shaft rated at 30,000 horsepower (33,000 horsepower for USS Chicago (SSN-721) and later) plus the electrical generation system. The S6G reactor plant was originally designed to use the D1G core 2 reactor first used on the Bainbridge-class guided missile cruisers rated at 148 MW. All submarines following (and including) USS Providence (SSN-719) were built with a D2W reactor rated at 165 MW. The D1G-2 reactors are being replaced with D2W reactors when the ships are refueled. ...more on Wikipedia about "S6G reactor"
The S7G was a design of United States Naval reactor that did not use control rods. It was tested in the early 1980s at the Modifications and Additions Reactor Facility (MARF). It consisted of a unique reactor core installed in a modified S5W reactor plant. ...more on Wikipedia about "S7G reactor"
The S8G reactor is the eighth nuclear fission reactor design finalized for use in powering U. S. Navy submarines by a division of the General Electric Corporation. ...more on Wikipedia about "S8G reactor"
S9G is the designation for a American naval nuclear reactor for submarines, the ninth in the series, designed and built by General Electric. It is used in Virginia-class submarines. ...more on Wikipedia about "S9G reactor"
SEFOR (Southwest Experimental Fast Oxide Reactor) is a deactivated experimental fast breeder reactor located near Strickler in northwest Arkansas. ...more on Wikipedia about "SEFOR"
Steam Generating Heavy Water Reactor (SGHWR) is a pressure tube type, heavy water moderated, light water cooled nuclear reactor. The steam generating heavy water reactor is in principle the same as a BWR but relies on a special heavy water material as the moderator whilst using conventional water as the primary coolant. They are similar in design to the CANDU, which uses pressure tubes and separates the coolant and moderator. The Advanced CANDU Reactor is designed to use boiling light water as its coolant. ...more on Wikipedia about "SGHWR"
The Shippingport power plant, located on the Ohio River in Beaver County, Pennsylvania about 25 miles from Pittsburgh was the first commercial nuclear power plant built in the United States. It began operating on December 2, 1957, and was in operation until October, 1982. ...more on Wikipedia about "Shippingport Reactor"
The SL-1, the Stationary Low-Power Reactor Number One, was a U.S. experimental military nuclear power reactor. It was destroyed in the first nuclear power plant accident in the United States. Part of the Army Nuclear Power Program, during design and build it was called the Argonne Low Power Reactor (ALPR). It was intended to provide electrical power and heat for small, remote military facilities, such as radar sites near the Arctic Circle, and those in the DEW Line. The design power was 3 megawatts (thermal). Operating power was 200 kW electrical, 400 kW thermal, for space heating. For testing it was located approximately forty miles (60 km) west of Idaho Falls, Idaho, in the National Reactor Testing Station, at . ...more on Wikipedia about "SL-1"
The SLOWPOKE (acronym for Safe Low-Power Kritical Experiment) is a low-energy, pool-type nuclear research reactor designed by Atomic Energy of Canada Limited (AECL) in the late 1960's. It is beryllium-reflected with a very low critical mass but provides neutron fluxes higher than available from a small particle accelerator or other radioactive sources. ...more on Wikipedia about "SLOWPOKE reactor"
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(SM-1) A 2 MWe nuclear reactor developed for the The US Army Nuclear Power Program (ANPP). It was located at Fort Belvoir, VA, and achived first criticality in 1957 (several months before the Shippingport Reactor) It was the first US nuclear power plant to be connected to an electrical grid. ...more on Wikipedia about "SM-1"
The Sodium-cooled fast reactor is a sodium cooled reactor that uses fast neutrons. It is designed for use with high level waste. ...more on Wikipedia about "Sodium-cooled fast reactor"
Spent nuclear fuel shipping casks are used to transport spent nuclear fuel used in nuclear power plants and research reactors to disposal sites such as the to-be-opened one at Yucca Mountain or the Nuclear reprocessing center at COGEMA La Hague site. Each shipping container is designed to maintain its integrity under normal transportation conditions and during hypothetical accident conditions. ...more on Wikipedia about "Spent nuclear fuel shipping cask"
SSTAR is an acronym for the "small, sealed, transportable, autonomous reactor" - being primarily researched and developed in the US by Lawrence Livermore National Laboratory. It is intended as a fast breeder reactor that is tamper resistant, passively safe, has a self-contained fuel source of Uranium-238 and an operative life of 30 years, which provides a constant power source between 10 and 100 megawatts. ...more on Wikipedia about "SSTAR"
A subcritical reactor is a nuclear fission reactor that produces fission without achieving criticality. Instead of a sustaining chain reaction, a subcritical reactor uses additional neutrons from an outside source. A reactor coupled to a particle accelerator to produce neutrons by spallation is called an Accelerator-Driven System (ADS). ...more on Wikipedia about "Subcritical reactor"
The Supercritical water reactor (SCWR) is a Generation IV reactor concept that uses supercritical water as the working fluid. SCWRs are basically LWRs operating at higher pressure and temperatures with a direct, once-through cycle. As most commonly envisioned, it would operate on a direct cycle, much like a BWR, but since it uses supercritical water (not to be confused with critical mass) as the working fluid, would have only one phase present, like the PWR. It could operate at much higher temperatures than both current PWRs and BWRs. ...more on Wikipedia about "Supercritical water reactor"
A thermal reactor is the most common category of nuclear reactor. ...more on Wikipedia about "Thermal reactor"
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The THTR-300 was a thorium high-temperature nuclear reactor rated at 300 MW electric (THTR-300). The Federal Republic of Germany and the German state of North Rhine Westphalia and Hochtemperatur-Kernkraftwerk GmbH (HKG) financed the THTR-300’s construction . Operations started on the plant in Hamm-Uentrop, Germany in 1983, and it was shut down September 1st, 1989 . The THTR was synchronized to the grid for the first time in 1985 and started full power operation in February 1987 . The THTR-300 served as a prototype for high-temperature reactors (HTR) and was the first to use a pebble bed design and TRISO fuel. The THTR-300 cost €2.05 billion and is predicted to cost an additional €425 million until December 2009 in decommissioning and other associated costs. ...more on Wikipedia about "THTR-300"
The Toshiba 4S (Super Safe, Small and Simple) is a “nuclear battery” reactor design. It requires only minimal staffing. ...more on Wikipedia about "Toshiba 4S"
TRIGA is a class of small nuclear reactor designed and manufactured by General Atomics of the USA. TRIGA is an acronym of "Training, Research, Isotopes, General Atomics". ...more on Wikipedia about "TRIGA"
Work on nuclear marine propulsion started in the 1940s, and the first test reactor started up in USA in 1953. The first nuclear-powered submarine, USS Nautilus, put to sea in 1955. Much of the development work on naval reactors was done at the Idaho National Engineering Laboratory ( Naval Reactor Facility). ...more on Wikipedia about "United States Naval reactor"
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