ESBWR
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The Economic Simplified Boiling Water Reactor (ESBWR) is a
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 saf ...
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, signi ...
design derived from its predecessor, the Simplified Boiling Water Reactor (SBWR) and from the
Advanced Boiling Water Reactor The advanced boiling water reactor (ABWR) is a Generation III boiling water reactor. The ABWR is currently offered by GE Hitachi Nuclear Energy (GEH) and Toshiba. The ABWR generates electrical power by using steam to power a turbine connected ...
(ABWR). All are designs by
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 Hitach ...
(GEH), and are based on previous
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 nuc ...
designs.


Passive safety system

The
passive nuclear safety 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 saf ...
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 A reactor pressure vessel (RPV) in a nuclear power plant is the pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core. Classification of nuclear power reactors Russian Soviet era RBMK reactors have each fuel a ...
(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 allow for the efficient transfer of decay heat (created from nuclear decay) from the reactor to pools of water outside containmentthe Isolation Condenser System, the Gravity Driven Cooling System, and the Passive Containment Cooling System. These systems utilize natural circulation based on simple laws of physics to transfer the decay heat outside containment while maintaining water levels inside the reactor, keeping the nuclear fuel submerged in water and adequately cooled. In events where the reactor coolant pressure boundary remains intact, the Isolation Condenser System (ICS) is used to remove decay heat from the reactor and transfer it outside containment. The ICS system is a closed loop system that connects the reactor pressure vessel to a heat exchanger located in the upper elevation of the reactor building. Steam leaves the reactor through the ICS piping and travels to the ICS heat exchangers which are submerged in a large pool. The steam is condensed in the heat exchangers and the denser condensate then flows back down to the reactor to complete the cooling loop. Reactor coolant is cycled through this flow path to provide continuous cooling and to add water to the reactor core. In cases where the reactor coolant pressure boundary does not remain intact and water inventory in the core is being lost, the Passive Containment Cooling System (PCCS) and Gravity Driven Cooling System (GDCS) work in concert to maintain the water level in the core and remove decay heat from the reactor by transferring it outside containment. If the water level inside the reactor pressure vessel drops to a predetermined level, due to the loss of water inventory, the reactor is depressurized and the GDCS is initiated. It consists of large pools of water inside containment located above the reactor that are connected to the reactor pressure vessel. When the GDCS system is initiated, gravity forces water to flow from the pools into the reactor. The pools are sized to provide sufficient amounts of water to maintain the water at a level above the top of the nuclear fuel. After the reactor has been depressurized, the decay heat is transferred to the containment as water inside the reactor boils and exits the reactor pressure vessel into the containment in the form of steam. The PCCS consists of a set of heat exchangers located in the upper portion of the reactor building. The steam from the reactor rises through the containment to the PCCS heat exchangers where the steam is condensed. The condensate then drains from the PCCS heat exchangers back to the GDCS pools where it completes the cycle and drains back to the reactor pressure vessel. Both the ICS and PCCS heat exchangers are submerged in a pool of water large enough to provide 72 hours of reactor decay heat removal capability. The pool is vented to the atmosphere and is located outside of the containment. The combination of these features allows the pool to be refilled easily with low pressure water sources and installed piping. The reactor core is shorter than in conventional BWR plants to reduce the pressure drop over the fuel, thereby enabling natural circulation. There are 1,132 fuel rod bundles and the thermal power is 4,500
MWth The watt (symbol: W) is the unit of power or radiant flux in the International System of Units (SI), equal to 1 joule per second or 1 kg⋅m2⋅s−3. It is used to quantify the rate of energy transfer. The watt is named after James Wat ...
in the standardized SBWR. The nominal output is rated at 1594
MWe The watt (symbol: W) is the unit of power or radiant flux in the International System of Units (SI), equal to 1 joule per second or 1 kg⋅m2⋅s−3. It is used to quantify the rate of energy transfer. The watt is named after James Watt ...
gross and 1535
MWe The watt (symbol: W) is the unit of power or radiant flux in the International System of Units (SI), equal to 1 joule per second or 1 kg⋅m2⋅s−3. It is used to quantify the rate of energy transfer. The watt is named after James Watt ...
net, yielding an overall plant Carnot efficiency of approximately 35%. In case of an accident, the ESBWR can remain in a safe, stable state for 72 hours without any operator action or even electrical power. ESBWR safety systems are designed to operate normally in the event of station blackout, which prevented proper functioning of the emergency core cooling systems at the
Fukushima Daiichi Nuclear Power Plant The is a disabled nuclear power plant located on a site in the towns of Ōkuma and Futaba in Fukushima Prefecture, Japan. The plant suffered major damage from the magnitude 9.0 earthquake and tsunami that hit Japan on March 11, 2011. The ...
. Below the vessel, there is a piping structure that allows for cooling of the core during any very severe accident. These pipes facilitate cooling above and below the molten core with water. The final safety evaluation report accepted by the NRC reports an overall core damage frequency of 1.65 * 10−8 per year (i.e., roughly once every 60 million years).


NRC design review process

The ESBWR received a positive Safety Evaluation Report and Final Design Approval on March 9, 2011. On June 7, 2011, the NRC completed its public comment period. Final rule was issued on September 16, 2014, after two outstanding problems with GE-Hitachi's modeling of loads on the steam dryer were solved. In January 2014, GE Hitachi paid $2.7 million to resolve a lawsuit alleging it made false claims to the NRC about its analysis of the steam dryer. The NRC granted design approval in September 2014.


Construction and operation licences

However, in September 2015, at the request of owner
Entergy Entergy Corporation is a Fortune 500 integrated energy company engaged primarily in electric power production and retail distribution operations in the Deep South of the United States. Entergy is headquartered in New Orleans, Louisiana, and ge ...
, the NRC withdrew the
Combined Construction and Operating License The Combined Construction and Operating License (Regulatory Guide 1.206, COL) replaced the previous Draft Regulatory Guide 1145 as the licensing process for new nuclear power plants in the United States. It is a part of a newer "streamlined" proce ...
application for the first proposed ESBWR unit at Grand Gulf Nuclear Generating Station. On May 31, 2017, the Nuclear Regulatory Commission announced that it had authorized the issuance of a Combined License for
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 Powe ...
unit 3.NRC to Issue New Reactor License to Dominion for North Anna Site , May 31, 2017
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See also

*
Nuclear power Nuclear power is the use of nuclear reactions to produce electricity. Nuclear power can be obtained from nuclear fission, nuclear decay and nuclear fusion reactions. Presently, the vast majority of electricity from nuclear power is produced b ...
*
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 ...
* Economics of nuclear power plants *
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, sign ...
*
European Pressurized Reactor The EPR is a Generation III reactor, third generation pressurised water reactor design. It has been designed and developed mainly by Framatome (part of Areva between 2001 and 2017) and Électricité de France (EDF) in France, and Siemens in Germ ...
*
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 ...


Other Generation III+ designs

* EPR * US-APWR *
VVER-TOI The VVER-TOI or WWER-TOI (russian: text=Водо-водяной энергетический реактор типовой оптимизированный информатизированный, translit=Vodo-Vodyanoi Energetichesky Reactor Tipov ...
* ACR


References


External links


GE Energy ESBWR website

Status report 100 - Economic Simplified Boiling Water Reactor (ESBWR)
ARIS, IAEA, 01-08-2011








Design overview
published in ANS Nuclear News (2006). {{Nuclear fission reactors Nuclear power reactor types Nuclear power in the United States Boiling water reactors