This article has multiple issues. Please help improve it or discuss these issues on the talk page . (Learn how and when to remove these messages)
|
The B&W mPower was a proposed small modular reactor designed by Babcock & Wilcox, and to be built by Generation mPower LLC, a joint venture of Babcock & Wilcox and Bechtel. It was a Generation III+ integral pressurized water reactor (light water reactor) concept.
In March 2017, Bechtel withdrew from the joint venture and the project was terminated. [1] [2]
The reactor was unveiled by Babcock & Wilcox in June 2009. [3] [4] In July 2010, Babcock & Wilcox announced a formal alliance with Bechtel called Generation mPower LLC. [5] At the same time, Babcock & Wilcox announced that it would build a test facility for the mPower reactor design at the Center for Advanced Engineering and Research in Bedford County, Virginia. [6] In April 2011, Babcock & Wilcox received a $5 million grant from the Virginia Tobacco Indemnification and Community Revitalisation Commission for this test facility. [7] [8]
In June 2011 Generation mPower signed a letter of intent with the Tennessee Valley Authority for constructing up to six reactors at Clinch River Breeder Reactor site in Tennessee. [9] [10]
Generation mPower planned to apply to the Nuclear Regulatory Commission for design certification by 2013. [10] Babcock & Wilcox announced on February 20, 2013, that they had contracted with the Tennessee Valley Authority to apply for permits to build an mPower small modular reactor at TVA's Clinch River site in Oak Ridge, Tennessee. [11] [12]
In November 2012, mPower won a US Department of Energy funding competition for new Small modular reactor (SMR) designs. The competition was intended to accelerate development of SMRs. [13] The award was funded at $79 million in 2013, from a total of $150 million over five years, with a possibility of total government grants reaching $226 million or more. [14]
In 2013 Babcock & Wilcox had intended to sell a majority stake in the mPower joint venture, but in February 2014 announced it was unable to find a buyer. [15]
In February 2014, Jim Ferland, B&W's CEO, announced that spending on the mPower reactor development will be decreased by 75%. The official explanation was that the company had failed in its effort to find additional major investors to participate in the project. [16]
In April 2014, Babcock & Wilcox announced it was scaling back investment in the programme, projecting investment of up to $15 million annually. It stated:
"Without the ability to secure significant additional investors or customer engineering, procurement and construction contracts to provide the financial support necessary to develop and deploy mPower reactors, the current development pace will be slowed." [17]
In March 2017 Bechtel withdrew from the joint venture, citing the inability to find a utility company that would provide a site for a first reactor and an investor. [1] The development project was terminated, with Babcock & Wilcox paying Bechtel a $30 million settlement. [2] [18]
B&W mPower was a Generation III+ integral pressurized water reactor (light water reactor) with a modular design. The reactor and steam generator would be located in a single integrated reactor vessel located in an underground containment facility that would store all of the spent fuel. [4] The modular unit had a diameter of 4.5 metres (15 ft) and it was 23 metres (75 ft) high. The reactor core was 2 by 2 metres (6 ft 7 in by 6 ft 7 in). The steam generator was similar to Once Through Steam Generators (OTSG) used in existing B&W plants (i.e. Three Mile island). The unit had an air-cooled condenser giving 31% thermal efficiency, and passive safety systems. [19]
The reactor was planned to have a rated electrical output of 125–180 MWe. [19] When originally announced, the reactor had planned capacity of 125 MWe. [4] [19] Later the power was increased to 160 MWe and then to 180 MWe. [19] In its pre-application design certification interaction with the Nuclear Regulatory Commission, the reactor's rated capacity was described as 500MWt of thermal power and 160 MWe of electrical power. [20]
The reactor was designed for an expected lifetime of 60 years. [4] [20] [21] [22]
B&W mPower uses standard fuel enriched to 5%, similar to the fuel loaded in the other PWRs. [19] It was designed for a 4-year refueling cycle. In the process of refuelling, the entire core will be completely removed in a single evolution, and replaced in a second separate evolution, making the core nearly "plug and play", unlike traditional reactors, which require fuel handling and movement of individual fuel rods during a refueling outage. [19] The entire used core, once removed, can be placed in storage in the spent fuel pool next to the IRV in the containment, which was designed to hold an entire 60 years worth of used fuel, and was accessible by the containment gantry crane located above the IRV within the containment. [21]
The mPower incorporates several features of the boiling water reactor (BWR). Like a BWR, the mPower reactor's primary coolant/moderator was highly purified water (with no boric acid). The Reactor Water Cleanup System ensures that primary system water remains pure. Similar to the ABWR, the mPower reactor had integral coolant recirculation pumps inside the Integral Reactor Vessel (IRV). The mPower reactor control rods are inserted from the top of the core and inserted upon scram under gravity. All of the primary coolants were in the liquid phase during normal operation.[ citation needed ]
The integral once-through steam generator was an advanced derivative of the steam generators used in older B&W designs (Davis Besse). Control rod drives do not penetrate the IRV, as in the light water reactors of today, but are instead wholly enclosed within the IRV. Burnable neutron absorbers within the fuel and control rod inventory are used to suppress hot excess reactivity. Cold shut-down was accomplished with control rod insertion (as in BWRs).[ citation needed ]
The mPower was designed to produce superheated steam and would not require steam separators and dryers before admitting steam into the high-pressure turbine.[ citation needed ]
The mPower was designed to eliminate the potential loss of coolant accidents as the integral reactor vessel would not have a large cold or hot leg piping; it contains the entire primary coolant loop within the reactor pressure vessel with automatic primary loop depressurization. If secondary cooling was lost, creating an effective loss of standard heat removal, there are water supplies located above and within the containment that can cool the vessel with gravity-driven cooling. Heat removal can be used if these systems are exhausted, such as by flooding the containment and establishing natural circulation, as no electrically driven pumps are required. [23]
A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. 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 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. Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of thermal-neutron reactor.
BWX Technologies, Inc., headquartered in Lynchburg, Virginia, USA is a supplier of nuclear components and fuel to the U.S.
Babcock & Wilcox Enterprises, Inc. is an American energy technology and service provider that is active and has operations in many international markets with its headquarters in Akron, Ohio. Historically, the company is best known for their steam boilers.
A containment building is a reinforced steel, concrete or lead structure enclosing a nuclear reactor. It is designed, in any emergency, to contain the escape of radioactive steam or gas to a maximum pressure in the range of 275 to 550 kPa. The containment is the fourth and final barrier to radioactive release, the first being the fuel ceramic itself, the second being the metal fuel cladding tubes, the third being the reactor vessel and coolant system.
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 to a generator; the steam is boiled from water using heat generated by fission reactions within nuclear fuel. Kashiwazaki-Kariwa unit 6 is considered the first Generation III reactor in the world.
The supercritical water reactor (SCWR) is a concept Generation IV reactor, designed as a light water reactor (LWR) that operates at supercritical pressure. The term critical in this context refers to the critical point of water, and should not be confused with the concept of criticality of the nuclear reactor.
Generation IVreactors are nuclear reactor design technologies that are envisioned as successors of generation III reactors. The Generation IV International Forum (GIF) – an international organization that coordinates the development of generation IV reactors – specifically selected six reactor technologies as candidates for generation IV reactors. The designs target improved safety, sustainability, efficiency, and cost. The World Nuclear Association in 2015 suggested that some might enter commercial operation before 2030.
A steam generator is a heat exchanger used to convert water into steam from heat produced in a nuclear reactor core. It is used in pressurized water reactors (PWRs), between the primary and secondary coolant loops. It is also used in liquid metal cooled reactors (LMRs), pressurized heavy-water reactors (PHWRs), and gas-cooled reactors (GCRs).
The water-water energetic reactor (WWER), or VVER is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress. The idea of such a reactor was proposed at the Kurchatov Institute by Savely Moiseevich Feinberg. VVER were originally developed before the 1970s, and have been continually updated. They were one of the initial reactors developed by the USSR, the other being the infamous RBMK. As a result, the name VVER is associated with a wide variety of reactor designs spanning from generation I reactors to modern generation III+ reactor designs. Power output ranges from 70 to 1300 MWe, with designs of up to 1700 MWe in development. The first prototype VVER-210 was built at the Novovoronezh Nuclear Power Plant.
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.
A nuclear reactor coolant is a coolant in a nuclear reactor used to remove heat from the nuclear reactor core and transfer it to electrical generators and the environment. Frequently, a chain of two coolant loops are used because the primary coolant loop takes on short-term radioactivity from the reactor.
The small modular reactor (SMR) is a class of small nuclear fission reactor, designed to be built in a factory, shipped to operational sites for installation and then used to power buildings or other commercial operations. The term SMR refers to the size, capacity and modular construction. Reactor type and the nuclear processes may vary. Of the many SMR designs, the pressurized water reactor (PWR) is the most common. However, recently proposed SMR designs include: generation IV, thermal-neutron reactors, fast-neutron reactors, molten salt, and gas-cooled reactor models.
The Energy Multiplier Module is a nuclear fission power reactor under development by General Atomics. It is a fast-neutron version of the Gas Turbine Modular Helium Reactor (GT-MHR) and is capable of converting spent nuclear fuel into electricity and industrial process heat.
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.
Holtec International is a supplier of equipment and systems for the energy industry. Founded in Mount Laurel, New Jersey in 1986, Holtec International is a privately-held technology company with domestic operation centers in New Jersey, Florida, Ohio and Pennsylvania and worldwide in Brazil, India Japan, Mexico, Poland, South Africa, Spain, U.K. and Ukraine. It specializes in the design and manufacture of parts for nuclear reactors. The company sells equipment to manage spent nuclear fuel from nuclear reactors.
General Electric's BWR product line of boiling water reactors represents the designs of a relatively large (~18%) percentage of the commercial fission reactors around the world.
The integral molten salt reactor (IMSR) is a nuclear power plant design targeted at developing a commercial product for the small modular reactor (SMR) market. It employs molten salt reactor technology which is being developed by the Canadian company Terrestrial Energy.
A nuclear microreactor is a plug-and-play type of nuclear reactor which can be easily assembled and transported by road, rail or air. Microreactors are 100 to 1,000 times smaller than conventional nuclear reactors, and range in capacity from 1 to 20 megawatts, compared to 20 to 300 megawatts for small modular reactors (SMRs). Due to their size, they can be deployed to locations such as isolated military bases or communities affected by natural disasters. It can operate as part of the grid, independent of the grid, or as part of a small grid for electricity generation and heat treatment. They are designed to provide resilient, non-carbon emitting, and independent power in challenging environments. The nuclear fuel source for the majority of the designs is "High-Assay Low-Enriched Uranium", or HALEU.