Small modular reactors (SMRs) are nuclear fission reactors that are smaller than conventional reactors and centrally manufactured. They can be manufactured at a plant and brought to a site to be installed. Modular reactors allow for less on-site construction, increased containment efficiency, and enhanced safety due to passive nuclear safety features. SMRs have the advantage of integrating passive safety features that do not require human intervention. In the case of a problem, the passive safety features will act in the absence of human supervision. SMRs also require less staffing than conventional nuclear reactors. SMRs have been proposed as a way to bypass financial and safety barriers that have inhibited the construction of large conventional nuclear reactors in recent decades.
Several designs exist for SMR, ranging from scaled down versions of existing designs to entirely new generation IV designs. Both thermal-neutron reactors and fast-neutron reactors have been proposed, as well as molten salt and gas cooled reactor models.
A main hindrance to commercial use is licensing, since current regulatory regimes are adapted to conventional nuclear power plants. SMRs differ in terms of staffing, security and deployment time. One concern with SMRs is preventing proliferation of nuclear material that is simpler to access than a conventional large-scale reactor. Licensing time, cost and risk are critical elements for the success of SMRs. Studies by the US government evaluating the risks associated with SMRs have led to challenges licensing and deploying them.
Advantages
The main SMR advantage is that they can be manufactured and assembled at a central factory location. They can then be sent to their deployment site and be installed with little difficulty. However, SMR module transport is critical and needs further studies.
Another advantage is that a user can install their first unit, instantly generating revenue and cash flows, then later add other reactors as necessary — cutting back on financing times and saving on multi-year construction processes.
Some larger SMRs require more significant on-site construction, such as the 440 MWe 3-loop Rolls-Royce SMR. The firm is targeting a 500-day construction time.
SMR reactors have a much smaller footprint, e.g. the Rolls-Royce SMR reactor takes 40.000m2 instead of 400.000m2 for a traditional plant.
SMRs can be deployed essentially anywhere. Containment is more efficient, and proliferation concerns are much less. SMRs are more flexible and do not need to be hooked into the local power grid.
Electricity needs in remote locations are usually small and variable. Large plants produce so much power that they require a large grid to distribute their output. SMRs have a load-following design so that when electricity demands are low they can produce less electricity.
Many SMRs are designed to use new fuel ideas that allow for higher burnup and longer fuel cycles. Longer refueling intervals can decrease proliferation risks and lower chances of radiation escaping containment. For reactors in remote areas, accessibility can be troublesome, so longer fuel life can be helpful.
SMRs can power significant users of energy, such as large vessels or production facilities (e.g. water treatment/purification, or mines). Remote locations may have difficulty finding efficient, reliable energy sources. Small nuclear reactors may solve energy problems in many hard-to-reach places. Cogeneration is an option.
Because of the lack of trained personnel available in remote areas, SMRs have to be inherently safe. Many SMRs use passive or inherent safety features. Passive safety features are engineered, but do not require human input to work. A pressure release valve may have a spring that can be pushed back when pressure gets too high. Inherent safety features require no moving parts to work, depending on physical laws.
Types
SMRs come in multiple designs. Some are simplified versions of current reactors, others involve entirely new technologies. All proposed SMRs use nuclear fission. SMR designs include thermal-neutron reactors and fast-neutron reactors.
Thermal-neutron reactors
Thermal-neutron reactors rely on a moderator to slow neutrons and generally use 235
U as fissile material. Most operating reactors are of this type.
Fast reactors
Fast
reactors don't use moderators. Instead they rely on the nuclear fuel to
absorb higher speed neutrons. This usually means changing the fuel
arrangement within the core, or using different fuels. E.g., 239
Pu is more likely to absorb a high-speed neutron than 235
U.
Fast reactors can be breeder reactors.
These reactors release enough neutrons to transmute non-fissionable
elements into fissionable ones. A common use for a breeder reactor is to
surround the core in a "blanket" of 238
U, the most easily found isotope. Once the 238
U undergoes a neutron absorption reaction, it becomes 239
Pu, which can be removed from the reactor during refueling, and used as fuel once it has been prepared.
Cooling
Conventional reactors use water as a coolant. SMRs may use water, liquid metal, gas and molten salt as coolants.
Thermal/electrical generation
Traditionally, nuclear reactors use a coolant loop to heat water into steam, and use that steam to run turbines to generate electricity. Some gas-cooled reactor designs are meant to drive a gas-powered turbine, rather than boil water. Thermal energy can be used directly, without conversion. Heat can be used in hydrogen production and other commercial operations, such as desalination and the production of petroleum products (extracting oil from tar sands, creating synthetic oil from coal, etc.).
Staffing
Several SMR developers claimed that their designs would require fewer staff members because of the inherent/passive safety systems. Reactors such as the Toshiba 4S are designed to run with little supervision.
Load following
Nuclear plants have been historically deployed to cover the base load of the electricity demand.
Some plants might perform daily load cycling (i.e. load following) at between 50% and 100% of their rated power. adjusting output, "Load Following via Cogeneration" runs the reactor at a constant level, while diverting any excess power to an auxiliary use. A suitable cogeneration system needs:
- demand of electricity and/or heat in the region of 500 MWe–1.5 GWt;
- market demand;
- access to adequate input to process;
- flexibility: cogeneration might operate at full load during the night when the request of electricity is low, and be turned off during the daytime.
Economically, it is essential that the investment in the auxiliary system be profitable. District heating, desalination and hydrogen have been proposed as technically and economically feasible options. SMR can be ideal for desalination over night.
Waste reduction
Many
SMRs are fast reactors that are designed to have higher fuel burnup
rates, reducing the amount of waste. At higher neutron energy more fission products can be usually tolerated. As mentioned before, some SMRs are also breeder reactors that "burn" 235
U, but convert fertile materials such as 238
U (which occurs naturally at a much higher concentration than 235
U) into usable fuels.
Some reactors are designed to run on the thorium fuel cycle, which offers significantly reduced long-term waste radiotoxicity compared to the uranium cycle.
The traveling wave reactor uses the fuel that it breeds. It eliminates the need to remove the spent fuel and "clean" it before reusing any newly bred fuel.
Safety
Diverse safety features can be involved, depending on reactor design. Coolant systems can use natural circulation – convection – to eliminate pumps that could break down, and they keep removing decay heat after the reactor shuts down, so that the core doesn't overheat and melt. Negative temperature coefficients in the moderators and the fuels keep the fission reactions under control, causing the reaction to slow as temperature increases. While passive control is a key selling point, a functioning reactor may also need an active cooling system to back up the passive system, at higher cost. Additionally, SMR designs have less need for containment structures.
Some SMR designs site the reactor and spent-fuel storage pools underground. Smaller reactors would be easier to upgrade quickly and have better passive quality controls.
Economics
A key driver of SMRs are the claimed economies of scale, compared to larger reactors, that stem from the ability to prefabricate them in a manufacturing plant/factory. Some studies instead find the capital cost of SMRs to be practically equivalent to larger reactors. A key disadvantage is that the improved affordability can only be realised if the factory is built in the first place, and this is likely to require initial orders for 40–70 units.
Another economic advantage is that the construction cost is much less than that of constructing a much more complex, non-modular, large nuclear plant. This makes SMR a smaller-risk venture for power companies than other nuclear power plants. However, modularisation and modularity influence the economic competitiveness of SMRs. Financial and economic issues can hinder SMR construction.
Staffing costs per unit output increase as reactor size decreases, due because some costs are fixed. SMR staff costs per unit output can be as much as 190% higher than the fixed operating cost of large reactors.
In 2017 an Energy Innovation Reform Project study of eight companies looked at reactor models with capacity between 47.5 MWe and 1,648 MWe in development. The study reported average capital cost of $3,782/kW, average operating cost total of $21/MWh and levelized cost of electricity of $60/MWh.
Energy Impact Center founder Bret Kugelmass claimed that thousands of SMRs could be built in parallel, "thus reducing costs associated with long borrowing times for prolonged construction schedules and reducing risk premiums currently linked to large projects." GE Hitachi Nuclear Energy Executive Vice President Jon Ball agreed, saying the modular elements of SMRs would also help reduce costs associated with extended construction times.
Licensing
A major barrier is the licensing process, historically developed for large reactors, preventing the simple deployment of several identical units in different countries. In particular the US Nuclear Regulatory Commission process for licensing has focused mainly on large commercial reactors. The design and safety specifications, staffing requirements and licensing fees have all been geared toward reactors with an electrical output of more than 700MWe.
Licensing for SMRs has been an ongoing discussion. There was a workshop in October 2009 about licensing difficulties and another in June 2010, with a US congressional hearing in May 2010. With growing worries about climate change and greenhouse gas emissions, added to problems with hydrocarbon supplies from foreign countries and accidents like the BP oil rig explosion in the Gulf of Mexico, many US government agencies are working to push the development of different licensing for SMRs. However, some argue that weakening safety regulations to push the development of SMRs may cancel out their enhanced safety characteristics.
The U.S. Advanced Reactor Demonstration Program will help license and build two prototype SMRs during the 2020s, with up to $4 billion of government funding support.
Non-proliferation
Nuclear proliferation, or the use of nuclear materials to create weapons, is a concern for small modular reactors. As SMRs have lower generation capacity and are physically small, they are intended to be deployed in many more locations than existing nuclear plants. This means both at more sites in existing nuclear power states, and in more countries that previously did not have nuclear plants. It is also intended that SMR sites have much lower staffing levels than current nuclear plants. Because of the increased number of sites, with fewer staff, physical protection and security becomes an increased challenge which could increase proliferation risks.
Many SMRs are designed to lessen the danger of materials being
stolen or misplaced. Nuclear reactor fuel can be low-enriched uranium,
with a concentration of less than 20% of fissile 235
U.
This low quantity, non-weapons-grade uranium makes the fuel less desirable for weapons production.
Once the fuel has been irradiated,
the fission products mixed with the fissile materials are highly
radioactive and require special handling to remove safely, another
non-proliferation feature.
Some SMR designs are intended to have lifetime cores so the SMRs do not need refuelling. This improves proliferation resistance by not requiring any on-site nuclear fuel handling. But it also means that there will be large inventories of fissile material within the SMRs to sustain a long lifetime, which could make it a more attractive proliferation target. A 200 MWe 30-year core life light water SMR could contain about 2.5 tonnes of plutonium toward the end of its working life.
Light-water reactors designed to run on the thorium fuel cycle offer increased proliferation resistance compared to conventional uranium cycle, though molten salt reactors have a substantial risk.
The modular construction of SMRs is another useful feature. Because the reactor core is often constructed completely inside a central manufacturing facility, fewer people have access to the fuel before and after irradiation.
Reactor designs
Numerous new reactor designs have been proposed across the world. A small selection of the most notable current SMR designs is listed below.
Design Licensing Under construction Operational Cancelled Retired
Name | Gross power (MWe) | Type | Producer | Country | Status |
---|---|---|---|---|---|
4S | 10–50 | SFR | Toshiba | Japan | Detailed design |
ABV-6 | 6–9 | PWR | OKBM Afrikantov | Russia | Detailed design |
ACP100 | 125 | PWR | China National Nuclear Corporation | China | Under Construction |
TMSR-LF1 | 10MW | MSR | China National Nuclear Corporation | China | Under Construction |
ARC-100 | 100 | SFR | ARC Nuclear | Canada | Design: Vendor design review. One unit approved for construction at Point Lepreau Nuclear Generating Station in December 2019. |
MMR | 5 | MSR | Ultra Safe Nuclear Corp. | Canada | Licensing stage |
ANGSTREM | 6 | LFR | OKB Gidropress | Russia | Conceptual design |
B&W mPower | 195 | PWR | Babcock & Wilcox | United States | Cancelled in March 2017 |
BANDI-60 | 60 | PWR (floating) | KEPCO | South Korea | Detailed design |
BREST-OD-300 | 300 | LFR | Atomenergoprom | Russia | Under construction |
BWRX-300 | 300 | ABWR | GE Hitachi Nuclear Energy | United States | Licensing stage |
CAREM | 27–30 | PWR | CNEA | Argentina | Under construction |
Copenhagen Atomics Waste Burner | 50 | MSR | Copenhagen Atomics | Denmark | Conceptual design |
CMSR | 100 | MSR | Seaborg Technologies | Denmark | Conceptual design |
EGP-6 | 11 | RBMK | IPPE & Teploelektroproekt Design | Russia | Operating (not actively marketed due to legacy design, will be taken out of operation permanently in 2021) |
ELENA | 0.068 | PWR | Kurchatov Institute | Russia | Conceptual design |
Energy Well | 8.4 | MSR | cs:Centrum výzkumu Řež | Czechia | Conceptual design |
Flexblue | 160 | PWR | Areva TA / DCNS group | France | Conceptual design |
Fuji MSR | 200 | MSR | International Thorium Molten Salt Forum (ITMSF) | Japan | Conceptual design |
GT-MHR | 285 | GTMHR | OKBM Afrikantov | Russia | Conceptual design completed |
G4M | 25 | LFR | Gen4 Energy | United States | Conceptual design |
GT-MHR | 50 | GTMHR | General Atomics, Framatom | United States,France | Conceptual design |
IMSR400 | 185–192 | MSR | Terrestrial Energy | Canada | Conceptual design |
TMSR-500 | 500 | MSR | ThorCon | Indonesia | Conceptual design |
IRIS | 335 | PWR | Westinghouse-led | international | Design (Basic) |
KLT-40S | 35 | PWR | OKBM Afrikantov | Russia | Operating |
MHR-100 | 25–87 | HTGR | OKBM Afrikantov | Russia | Conceptual design |
MHR-T | 205.5x4 | HTGR | OKBM Afrikantov | Russia | Conceptual design |
MRX | 30–100 | PWR | JAERI | Japan | Conceptual design |
NP-300 | 100–300 | PWR | Areva TA | France | Conceptual design |
NuScale | 45 | PWR | NuScale Power LLC | United States | Licensing stage |
Nuward | 300–400 | PWR | consortium | France | Conceptual design, construction anticipated in 2030 |
PBMR-400 | 165 | HTGR | Eskom | South Africa | Cancelled. Postponed indefinitely |
RITM-200 | 50 | PWR | OKBM Afrikantov | Russia | Operational since October 2019 |
Rolls-Royce SMR | 440 | PWR | Rolls-Royce | United Kingdom | Design stage |
SEALER | 55 | LFR | LeadCold | Sweden | Design stage |
SMART | 100 | PWR | KAERI | South Korea | Licensed |
SMR-160 | 160 | PWR | Holtec International | United States | Conceptual design |
SVBR-100 | 100 | LFR | OKB Gidropress | Russia | Detailed design |
SSR-W | 300–1000 | MSR | Moltex Energy | United Kingdom | Conceptual design |
S-PRISM | 311 | FBR | GE Hitachi Nuclear Energy | United States/Japan | Detailed design |
TerraPower | 10 | TWR | Intellectual Ventures | United States | Conceptual design |
U-Battery | 4 | HTGR | U-Battery consortium | United Kingdom | Design and development work |
VBER-300 | 325 | PWR | OKBM Afrikantov | Russia | Licensing stage |
VK-300 | 250 | BWR | Atomstroyexport | Russia | Detailed design |
VVER-300 | 300 | BWR | OKB Gidropress | Russia | Conceptual design |
Westinghouse SMR | 225 | PWR | Westinghouse Electric Company | United States | Cancelled. Preliminary design completed. |
Xe-100 | 80 | HTGR | X-energy | United States | Conceptual design development |
Updated as of 2014. Some reactors are not included in IAEA Report. Not all IAEA reactors are listed there are added yet and some are added (anno 2021) that were not yet listed in the now dated IAEA report. |
Proposed sites
Canada
In 2018, the Canadian province of New Brunswick announced it would invest $10 million to attract SMR research to New Brunswick with a potential site for a demonstration project at the Point Lepreau Nuclear Generating Station. It was later announced that SMR proponents Advanced Reactor Concepts and Moltex would open offices in New Brunswick with the potential of developing sites at Lepreau.
On 1 December 2019, the Premiers of Ontario, New Brunswick and Saskatchewan signed a memorandum of understanding "committing to collaborate on the development and deployment of innovative, versatile and scalable nuclear reactors, known as Small Modular Reactors (SMRs)." They were later joined by Alberta in August 2020.
China
In July 2019 China National Nuclear Corporation announced it would start building a demonstration ACP100 SMR on the north-west side of the existing Changjiang Nuclear Power Plant by the end of the year.
On 7 June 2021, the construction of a demonstration ACP100 small modular reactor (SMR) at Changjiang in Hainan province has been approved by China's National Development and Reform Commission.
In July 2021 China National Nuclear Corporation (CNNC) has started construction of the first commercial onshore nuclear project using its homegrown “Linglong One” small modular reactor (SMR) design.
Poland
Polish chemical company Synthos declared plans to deploy a Hitachi BWRX-300 reactor (300 MW) in Poland by 2030. A feasibility study for the project was completed in December 2020 and licensing process started with Polish National Atomic Energy Agency.
United Kingdom
In 2016 it was reported that the UK Government was assessing sites for deploying SMRs in Wales - including the former Trawsfynydd nuclear power station - and on the site of former nuclear or coal-fired power stations in Northern England. Existing nuclear sites including Bradwell, Hartlepool, Heysham, Oldbury, Sizewell, Sellafield and Wylfa are thought to be possibilities. The target cost for a 440 MWe Rolls-Royce SMR unit is £1.8 billion for the fifth unit built. In 2020 it was reported that Rolls-Royce has plans to construct up to 16 SMRs in the UK. In 2019, the company received £18 million to begin designing the modular system, and the BBC claims that the government will provide an additional £200 million for the project as a part of its green plan for economic recovery.
United States
In December 2019 the Tennessee Valley Authority was authorized to receive an Early Site Permit (ESP) by the Nuclear Regulatory Commission for potentially siting an SMR at its Clinch River Site in Tennessee. This ESP will be valid for up to 20 years, and addresses site safety, environmental protection and emergency preparedness associated. TVA has not made a technology selection so this ESP is applicable for any of the light-water reactor SMR designs under development in the United States.
The Utah Associated Municipal Power Systems (UAMPS) announced a teaming partnership with Energy Northwest to explore siting a NuScale Power reactor in Idaho, possibly on the Department of Energy's Idaho National Laboratory.
The Galena Nuclear Power Plant in Galena, Alaska was a proposed micro nuclear reactor installation intended to reduce the costs and environmental pollution required to power the town. It was a potential deployment for the Toshiba 4S reactor.