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ESBWR
The Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor design derived from its predecessor, the Simplified Boiling Water Reactor (SBWR) and from the Advanced Boiling Water Reactor (ABWR). All are designs by GE Hitachi Nuclear Energy (GEH), and are based on previous Boiling Water Reactor designs. Passive safety system The passive nuclear safety systems in an ESBWR operate without using any pumps, which creates increased design safety, integrity, and reliability, while simultaneously reducing overall reactor cost. It also uses natural circulation to drive coolant flow within the reactor pressure vessel (RPV); this results in fewer systems to maintain, and precludes significant BWR casualties such as recirculation line breaks. There are no circulation pumps or associated piping, power supplies, heat exchangers, instrumentation, or controls needed for these systems. ESBWR's passive safety systems include a combination of three systems that ...
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Esbwr
The Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor design derived from its predecessor, the Simplified Boiling Water Reactor (SBWR) and from the Advanced Boiling Water Reactor (ABWR). All are designs by GE Hitachi Nuclear Energy (GEH), and are based on previous Boiling Water Reactor designs. Passive safety system The passive nuclear safety systems in an ESBWR operate without using any pumps, which creates increased design safety, integrity, and reliability, while simultaneously reducing overall reactor cost. It also uses natural circulation to drive coolant flow within the reactor pressure vessel (RPV); this results in fewer systems to maintain, and precludes significant BWR casualties such as recirculation line breaks. There are no circulation pumps or associated piping, power supplies, heat exchangers, instrumentation, or controls needed for these systems. ESBWR's passive safety systems include a combination of three systems that ...
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Boiling Water Reactor
A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is a design different from a Soviet graphite-moderated RBMK. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), which is also a type of light water nuclear reactor. The main difference between a BWR and PWR is that in a BWR, the reactor core heats water, which turns to steam and then drives a steam turbine. In a PWR, the reactor core heats water, which does not boil. This hot water then exchanges heat with a lower pressure system, which turns water into steam that drives the turbine. The BWR was developed by the Argonne National Laboratory and General Electric (GE) in the mid-1950s. The main present manufacturer is GE Hitachi Nuclear Energy, which specializes in the design and construction of this type of reactor. Overview A boiling water reactor uses demineralized water as a coolant and neu ...
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GE Hitachi Nuclear Energy
GE Hitachi Nuclear Energy (GEH) is a provider of advanced reactors and nuclear services. It is headquartered in Wilmington, North Carolina, United States. Established in June 2007, GEH is a nuclear alliance created by General Electric and Hitachi. In Japan, the alliance is Hitachi-GE Nuclear Energy. In November 2015, Jay Wileman was appointed CEO. History In 1955, the Atomic Power Equipment Department was established by GE. Two years later, in 1957: GE's first privately financed nuclear power reactor provides electricity for commercial use in Vallecitos, California. Additionally, in 1960, GE made and contributed to the Dresden Nuclear Power Station in Chicago. In the 1960s, it got involved in constructing and building the Boiling water reactor (BWR). The research into the project continued in the next 50 years resulting in production of 6 different BWR generations. In 1997, the GE-Hitachi U.S. Advanced boiling water reactor (ABWR) design was certified as a final design in fi ...
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North Anna Nuclear Generating Station
The North Anna Nuclear Generating Station is a nuclear power plant on a site in Louisa County, Virginia, in the Mid-Atlantic United States. The site is operated by Dominion Generation company and is jointly owned by the Dominion Virginia Power corporation (88.4%) and by the Old Dominion Electric Cooperative (11.6%). The plant has two Westinghouse pressurized water reactors which went on-line in 1978 and 1980, respectively. Together the reactors generate 1.79 gigawatts of power, which is distributed mainly to the greater Richmond area and to Northern Virginia. In March 2003, the Nuclear Regulatory Commission approved 20 year license extensions for both Units 1 & 2. An artificial lake, Lake Anna, was constructed on the North Anna River to provide a reservoir of water coolant for use with the nuclear plant. Dominion Energy currently owns nuclear power plants in Virginia (North Anna, Surry), Connecticut (Millstone), South Carolina ( Virgil C. Summer Nuclear Generating Sta ...
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Boiling Water Reactor Safety Systems
Boiling water reactor safety systems are nuclear safety systems constructed within boiling water reactors in order to prevent or mitigate environmental and health hazards in the event of accident or natural disaster. Like the pressurized water reactor, the BWR reactor core continues to produce heat from radioactive decay after the fission reactions have stopped, making a core damage incident possible in the event that all safety systems have failed and the core does not receive coolant. Also like the pressurized water reactor, a boiling water reactor has a negative void coefficient, that is, the neutron (and the thermal) output of the reactor decreases as the proportion of steam to liquid water increases inside the reactor. However, unlike a pressurized water reactor which contains no steam in the reactor core, a sudden increase in BWR steam pressure (caused, for example, by the actuation of the main steam isolation valve (MSIV) from the reactor) will result in a sudden decre ...
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Generation III Reactor
Generation III reactors, or Gen III reactors, are a class of nuclear reactors designed to succeed Generation II reactors, incorporating evolutionary improvements in design. These include improved fuel technology, higher thermal efficiency, significantly enhanced safety systems (including passive nuclear safety), and standardized designs intended to reduce maintenance and capital costs. They are promoted by the Generation IV International Forum (GIF). The first Generation III reactors to begin operation were Kashiwazaki 6 and 7 advanced boiling water reactors (ABWRs) in 1996 and 1997. Since 2012, both have been shut down due to security concerns. Due to the prolonged period of stagnation in the construction of new reactors and the continued (albeit declining) popularity of Generation II/II+ designs in new construction, relatively few third generation reactors have been built. Overview The older Gen II reactors comprise the vast majority of current nuclear reactors. Gen III re ...
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Generation III Reactor
Generation III reactors, or Gen III reactors, are a class of nuclear reactors designed to succeed Generation II reactors, incorporating evolutionary improvements in design. These include improved fuel technology, higher thermal efficiency, significantly enhanced safety systems (including passive nuclear safety), and standardized designs intended to reduce maintenance and capital costs. They are promoted by the Generation IV International Forum (GIF). The first Generation III reactors to begin operation were Kashiwazaki 6 and 7 advanced boiling water reactors (ABWRs) in 1996 and 1997. Since 2012, both have been shut down due to security concerns. Due to the prolonged period of stagnation in the construction of new reactors and the continued (albeit declining) popularity of Generation II/II+ designs in new construction, relatively few third generation reactors have been built. Overview The older Gen II reactors comprise the vast majority of current nuclear reactors. Gen III re ...
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Grand Gulf Nuclear Generating Station
Grand Gulf Nuclear Station is a nuclear power station with one operational GE BWR reactor (General Electric boiling water reactor). It lies on a site near Port Gibson, Mississippi. The site is wooded and contains two lakes. The plant has a 520-foot natural draft cooling tower. As of January 2023, the plant employs 675 people. Grand Gulf's reactor is the most powerful in the US and the 7th most powerful in the world, with a core power of 4408 MWth yielding a nominal gross electrical output of 1443 MWe. Grand Gulf is operated by Entergy, which also owns 90% of the station through their subsidiary, System Energy Resources Inc. The other 10% is owned by Cooperative Energy. Units 2 and 3 Adjacent to the operating Grand Gulf station, is an unfinished concrete structure that was to be the containment for Unit 2, a twin to the existing Unit 1. In December 1979, staggered by construction cost, Entergy (then called Middle South Utilities) stopped work on Unit 2. On September 22 ...
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Nuclear Power 2010 Program
The "Nuclear Power 2010 Program" was launched in 2002 by President George W. Bush in 2002, 13 months after the beginning of his presidency, in order to restart orders for nuclear power reactors in the U.S. by providing subsidies for a handful of Generation III+ demonstration plants. The expectation was that these plants would come online by 2010, but it was not met. In March 2017, the leading nuclear-plant maker, Westinghouse Electric Company, filed for bankruptcy due to losing over $9 billion in construction losses from working on two nuclear plants. This loss was partly caused by safety concerns due to the Fukushima disaster, Germany's Energiewende, the growth of solar and wind power, and low natural gas prices. Overview The "Nuclear Power 2010 Program" was unveiled by the U.S. Secretary of Energy Spencer Abraham on February 14, 2002 as one means towards addressing the expected need for new power plants. The program was a joint government/industry cost-shared effort to ident ...
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Economics Of Nuclear Power Plants
Nuclear power construction costs have varied significantly across the world and in time. Large and rapid increases in cost occurred during the 1970s, especially in the United States. Recent cost trends in countries such as Japan and Korea have been very different, including periods of stability and decline in costs. New nuclear power plants typically have high capital expenditure for building plants. Fuel, operational, and maintenance costs are relatively small components of the total cost. The long service life and high capacity factor of nuclear power plants allow sufficient funds for ultimate plant decommissioning and waste storage and management to be accumulated, with little impact on the price per unit of electricity generated. Additionally, measures to mitigate climate change such as a carbon tax or carbon emissions trading, favor the economics of nuclear power over fossil fuel power. Nuclear power is cost competitive with renewable generation when capital cost is in th ...
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Passively Safe
Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the part of the operator or electrical/electronic feedback in order to bring the reactor to a safe shutdown state, in the event of a particular type of emergency (usually overheating resulting from a loss of coolant or loss of coolant flow). Such design features tend to rely on the engineering of components such that their predicted behaviour would slow down, rather than accelerate the deterioration of the reactor state; they typically take advantage of natural forces or phenomena such as gravity, buoyancy, pressure differences, conduction or natural heat convection to accomplish safety functions without requiring an active power source. Many older common reactor designs use passive safety systems to a limited extent, rather, relying on active safety systems such as diesel powered motors. Some newer reactor designs feature more passive ...
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Nuclear Safety In The United States
Nuclear safety in the United States is governed by federal regulations issued by the Nuclear Regulatory Commission (NRC). The NRC regulates all nuclear plants and materials in the United States except for nuclear plants and materials controlled by the U.S. government, as well those powering naval vessels. The 1979 Three Mile Island accident was a pivotal event that led to questions about U.S. nuclear safety. Earlier events had a similar effect, including a 1975 fire at Browns Ferry Nuclear Power Plant, Browns Ferry and the 1976 testimonials of three concerned GE nuclear engineers, the GE Three. In 1981, workers inadvertently reversed pipe restraints at the Diablo Canyon Power Plant reactors, compromising seismic protection systems, which further undermined confidence in nuclear safety. All of these well-publicised events, undermined public support for the U.S. nuclear industry in the 1970s and the 1980s. In 2002, the USA had what former NRC Commissioner Victor Gilinsky termed "its ...
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