Molten-salt reactor



A molten-salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt with a fissionable material.

Two research MSRs operated in the United States in the mid-20th century. The 1950s Aircraft Reactor Experiment (ARE) was primarily motivated by the technology's compact size, while the 1960s Molten-Salt Reactor Experiment (MSRE) aimed to demonstrate a nuclear power plant using a thorium fuel cycle in a breeder reactor.

Increased research into Generation IV reactor designs renewed interest in the 21st century with multiple nations starting projects. As of May 2023, China had not announced the ignition of its TMSR-LF1 thorium unit following its scheduled date of February 2023.

MSRs eliminate the nuclear meltdown scenario present in water-cooled reactors because the fuel mixture is kept in a molten state. The fuel mixture is designed to drain without pumping from the core to a containment vessel in emergency scenarios, where the fuel solidifies, quenching the reaction. In addition, hydrogen evolution does not occur. This eliminates the risk of hydrogen explosions (as in the Fukushima nuclear disaster). They operate at or close to atmospheric pressure, rather than the 75–150 times atmospheric pressure of a typical light-water reactor (LWR). This reduces the need and cost for reactor pressure vessels. The gaseous fission products (Xe and Kr) have little solubility in the fuel salt, and can be safely captured as they bubble out of the fuel, rather than increasing the pressure inside the fuel tubes, as happens in conventional reactors. MSRs can be refueled while operating (essentially online-nuclear reprocessing) while conventional reactors shut down for refueling (notable exceptions include pressure tube heavy water reactors like the CANDU or the Atucha-class PHWRs, and British-built gas-cooled reactors such as Magnox, AGR). MSR operating temperatures are around 700 C, significantly higher than traditional LWRs at around 300 C. This increases electricity-generation efficiency and process-heat opportunities.

Relevant design challenges include the corrosivity of hot salts and the changing chemical composition of the salt as it is transmuted by the neutron flux.

Properties
MSRs, especially those with fuel in the molten salt, offer lower operating pressures, and higher temperatures. In this respect an MSR is more similar to a liquid metal cooled reactor than to a conventional light water cooled reactor. MSR designs are often breeding reactors with a closed fuel cycle—as opposed to the once-through fuel currently used in conventional nuclear power generators.

MSRs exploit a negative temperature coefficient of reactivity and a large allowable temperature rise to prevent criticality accidents. For designs with the fuel in the salt, the salt thermally expands immediately with power excursions. In conventional reactors the negative reactivity is delayed since the heat from the fuel must be transferred to the moderator. An additional method is to place a separate, passively cooled container below the reactor. Fuel drains into the container during malfunctions or maintenance, which stops the reaction.

The temperatures of some designs are high enough to produce process heat, which led them to be included on the GEN-IV roadmap.

Advantages
MSRs offer many potential advantages over light water reactors:
 * Passive decay heat removal is achieved in MSRs. In some designs, the fuel and the coolant are a single fluid, so a loss of coolant carries the fuel with it. Fluoride salts dissolve poorly in water, and do not form burnable hydrogen. The molten salt coolant is not damaged by neutron bombardment, though the reactor vessel is.
 * A low-pressure MSR does not require an expensive, steel core containment vessel, piping, and safety equipment. However, most MSR designs place radioactive fluid in direct contact with pumps and heat exchangers.
 * MSRs enable cheaper closed nuclear fuel cycles, because they can operate with slow neutrons. Closed fuel cycles can reduce environmental impacts: chemical separation turns long-lived actinides into reactor fuel. Discharged wastes are mostly fission products with shorter half-lives. This can reduce the needed containment to 300 years versus the tens of thousands of years needed by light-water reactor spent fuel.
 * The fuel's liquid phase can be pyroprocessed to separate fission products from fuels. This may have advantages over conventional reprocessing.
 * Fuel rod fabrication is replaced with salt synthesis.
 * Some designs are compatible with fast neutrons, which can "burn" transuranic elements such as, (reactor grade plutonium) from LWRs.
 * An MSR can react to load changes in under 60 seconds (unlike LWRs that suffer from xenon poisoning).
 * Molten-salt reactors can run at high temperatures, yielding high thermal efficiency. This reduces size, expense, and environmental impacts.
 * MSRs can offer a high "specific power", (high power at low mass), as demonstrated by ARE.
 * Potential neutron economy suggests that MSR may be able to exploit the neutron-poor thorium fuel cycle.

Disadvantages

 * In circulating-fuel-salt designs, radionuclides dissolved in fuel contact equipment such as pumps and heat exchangers, potentially requiring fully remote maintenance.
 * Some MSRs require onsite chemical processing to manage core mixture and remove fission products.
 * Regulatory changes to accommodate non-traditional design features
 * Some MSR designs rely on expensive nickel alloys to contain the molten salt. Such alloys are prone to embrittlement under high neutron flux.
 * Corrosion risk. Molten salts require careful management of their oxidation state to manage corrosion risks. This is particularly challenging for circulating designs, in which a mix of isotopes and their decay products circulate through the reactor. Static designs benefit from modularising the problem: the fuel salt is contained within fuel pins whose regular replacement, primarily due to neutron irradiation, is normalized; while the coolant salt has a simpler chemical composition and does not pose a corrosion risk either to the fuel pins or to the reactor vessel. MSRs developed at ORNL in the 1960s were safe to operate only for a few years, and operated at only about 650 C. Corrosion risks include dissolution of chromium by liquid fluoride thorium salts at greater than 700 C, hence endangering stainless steel components. Neutron radiation can transmute common alloying agents such as Co and Ni, shortening lifespan. Lithium salts such as FLiBe warrant the use of to reduce tritium generation (tritium can permeate stainless steels, cause embrittlement, and escape into the environment). ORNL developed Hastelloy N to help address these issues, while other structural steels may be acceptable, such as 316H, 800H, and inconel 617.
 * Some MSR designs can be turned into a breeder reactor to produce weapons-grade nuclear material.
 * MSRE and ARE used high enriched uranium approaching weapons-grade. These levels would be illegal in most modern power plant regulatory regimes. Most modern designs employ lower-enriched fuels.
 * Neutron damage to solid moderator materials can limit the core lifetime. For example, MSRE was designed so that its graphite moderator had loose tolerances, so neutron damage could change them without consequences. "Two fluid" MSR designs do not use graphite piping because graphite changes size when bombarded with neutrons. MSRs using fast neutrons cannot use graphite, because it moderates neutrons.
 * Thermal MSRs have lower breeding ratios than fast-neutron breeders, though their doubling time may be shorter.

Coolant
MSRs can be cooled in various ways, including using molten salts.

Molten-salt-cooled solid-fuel reactors are variously called "molten-salt reactor system" in the Generation IV proposal, molten-salt converter reactors (MSCR), advanced high-temperature reactors (AHTRs), or fluoride high-temperature reactors (FHR, preferred DOE designation).

FHRs cannot reprocess fuel easily and have fuel rods that need to be fabricated and validated, requiring up to twenty years from project inception. FHR retains the safety and cost advantages of a low-pressure, high-temperature coolant, also shared by liquid metal cooled reactors. Notably, steam is not created in the core (as is present in boiling water reactors), and no large, expensive steel pressure vessel (as required for pressurized water reactors). Since it can operate at high temperatures, the conversion of the heat to electricity can use an efficient, lightweight Brayton cycle gas turbine.

Much of the current research on FHRs is focused on small, compact heat exchangers that reduce molten salt volumes and associated costs.

Molten salts can be highly corrosive and corrosivity increases with temperature. For the primary cooling loop, a material is needed that can withstand corrosion at high temperatures and intense radiation. Experiments show that Hastelloy-N and similar alloys are suited to these tasks at operating temperatures up to about 700 °C. However, operating experience is limited. Still higher operating temperatures are desirable—at 850 C thermochemical production of hydrogen becomes possible. Materials for this temperature range have not been validated, though carbon composites, molybdenum alloys (e.g. TZM), carbides, and refractory metal based or ODS alloys might be feasible.

Fused salt selection
The salt mixtures are chosen to make the reactor safer and more practical.

Fluorine
Fluorine has only one stable isotope, and does not easily become radioactive under neutron bombardment. Compared to chlorine and other halides, fluorine also absorbs fewer neutrons and slows ("moderates") neutrons better. Low-valence fluorides boil at high temperatures, though many pentafluorides and hexafluorides boil at low temperatures. They must be very hot before they break down into their constituent elements. Such molten salts are "chemically stable" when maintained well below their boiling points. Fluoride salts dissolve poorly in water, and do not form burnable hydrogen.

Chlorine
Chlorine has two stable isotopes ( and ), as well as a slow-decaying isotope between them which facilitates neutron absorption by.

Chlorides permit fast breeder reactors to be constructed. Much less research has been done on reactor designs using chloride salts. Chlorine, unlike fluorine, must be purified to isolate the heavier stable isotope,, thus reducing production of sulfur tetrachloride that occurs when absorbs a neutron to become , then degrades by beta decay to.

Lithium
Lithium must be in the form of purified, because effectively captures neutrons and produces tritium. Even if pure is used, salts containing lithium cause significant tritium production, comparable with heavy water reactors.

Mixtures
Reactor salts are usually close to eutectic mixtures to reduce their melting point. A low melting point simplifies melting the salt at startup and reduces the risk of the salt freezing as it is cooled in the heat exchanger.

Due to the high "redox window" of fused fluoride salts, the redox potential of the fused salt system can be changed. Fluorine-lithium-beryllium ("FLiBe") can be used with beryllium additions to lower the redox potential and nearly eliminate corrosion. However, since beryllium is extremely toxic, special precautions must be engineered into the design to prevent its release into the environment. Many other salts can cause plumbing corrosion, especially if the reactor is hot enough to make highly reactive hydrogen.

To date, most research has focused on FLiBe, because lithium and beryllium are reasonably effective moderators and form a eutectic salt mixture with a lower melting point than each of the constituent salts. Beryllium also performs neutron doubling, improving the neutron economy. This process occurs when the beryllium nucleus emits two neutrons after absorbing a single neutron. For the fuel carrying salts, generally 1% or 2% (by mole) of UF4 is added. Thorium and plutonium fluorides have also been used.

Fused salt purification
Techniques for preparing and handling molten salt were first developed at ORNL. The purpose of salt purification is to eliminate oxides, sulfur and metal impurities. Oxides could result in the deposition of solid particles in reactor operation. Sulfur must be removed because of its corrosive attack on nickel-based alloys at operational temperature. Structural metal such as chromium, nickel, and iron must be removed for corrosion control. A water content reduction purification stage using HF and helium sweep gas was specified to run at 400 °C. Oxide and sulfur contamination in the salt mixtures were removed using gas sparging of HF/H2 mixture, with the salt heated to 600 °C. Structural metal contamination in the salt mixtures were removed using hydrogen gas sparging, at 700 °C. Solid ammonium hydrofluoride was proposed as a safer alternative for oxide removal.

Fused salt processing
The possibility of online processing can be an MSR advantage. Continuous processing would reduce the inventory of fission products, control corrosion and improve neutron economy by removing fission products with high neutron absorption cross-section, especially xenon. This makes the MSR particularly suited to the neutron-poor thorium fuel cycle. Online fuel processing can introduce risks of fuel processing accidents, which can trigger release of radio isotopes.

In some thorium breeding scenarios, the intermediate product protactinium would be removed from the reactor and allowed to decay into highly pure uranium-233, an attractive bomb-making material. More modern designs propose to use a lower specific power or a separate thorium breeding blanket. This dilutes the protactinium to such an extent that few protactinium atoms absorb a second neutron or, via a (n, 2n) reaction (in which an incident neutron is not absorbed but instead knocks a neutron out of the nucleus), generate. Because has a short half-life and its decay chain contains hard gamma emitters, it makes the isotopic mix of uranium less attractive for bomb-making. This benefit would come with the added expense of a larger fissile inventory or a 2-fluid design with a large quantity of blanket salt.

The necessary fuel salt reprocessing technology has been demonstrated, but only at laboratory scale. A prerequisite to full-scale commercial reactor design is the R&D to engineer an economically competitive fuel salt cleaning system.

Fuel reprocessing
Reprocessing refers to the chemical separation of fissionable uranium and plutonium from spent fuel. Such recovery could increase the risk of nuclear proliferation. In the United States the regulatory regime has varied dramatically across administrations.

Costs and economics
A systematic literature review from 2020 concludes that there is very limited information on economics and finance of MSRs, with low quality of the information and that cost estimations are uncertain.

In the specific case of the stable salt reactor (SSR) where the radioactive fuel is contained as a molten salt within fuel pins and the primary circuit is not radioactive, operating costs are likely to be lower.

Types of molten-salt reactors
While many design variants have been proposed, there are three main categories regarding the role of molten salt:

The use of molten salt as fuel and as coolant are independent design choices – the original circulating-fuel-salt MSRE and the more recent static-fuel-salt SSR use salt as fuel and salt as coolant; the DFR uses salt as fuel but metal as coolant; and the FHR has solid fuel but salt as coolant.

Designs
MSRs can be burners or breeders. They can be fast or thermal or epithermal. Thermal reactors typically employ a moderator (usually graphite) to slow the neutrons down and moderate temperature. They can accept a variety of fuels (low-enriched uranium, thorium, depleted uranium, waste products) and coolants (fluoride, chloride, lithium, beryllium, mixed). Fuel cycle can be either closed or once-through. They can be monolithic or modular, large or small. The reactor can adopt a loop, modular or integral configuration. Variations include:

Molten salt fast reactor
The molten-salt fast reactor (MSFR) is a proposed design with the fuel dissolved in a fluoride salt coolant. The MSFR is one of the two variants of MSRs selected by the Generation IV International Forum (GIF) for further development, the other being the FHR or AHTR. The MSFR is based on a fast neutron spectrum and is believed to be a long-term substitute to solid-fueled fast reactors. They have been studied for almost a decade, mainly by calculations and determination of basic physical and chemical properties in the European Union and Russian Federation. A MSFR is regarded sustainable because there are no fuel shortages. Operation of a MSFR does in theory not generate or require large amounts of transuranic (TRU) elements. When steady state is achieved in a MSFR, there is no longer a need for uranium enrichment facilities.

MSFRs may be breeder reactors. They operate without a moderator in the core such as graphite, so graphite life-span is no longer a problem. This results in a breeder reactor with a fast neutron spectrum that operates in the Thorium fuel cycle. MSFRs contain relatively small initial inventories of. MSFRs run on liquid fuel with no solid matter inside the core. This leads to the possibility of reaching specific power that is much higher than reactors using solid fuel. The heat produced goes directly into the heat transfer fluid. In the MSFR, a small amount of molten salt is set aside to be processed for fission product removal and then returned to the reactor. This gives MSFRs the capability of reprocessing the fuel without stopping the reactor. This is very different compared to solid-fueled reactors because they have separate facilities to produce the solid fuel and process spent nuclear fuel. The MSFR can operate using a large variety of fuel compositions due to its on-line fuel control and flexible fuel processing.

The standard MSFR would be a 3000 MWth reactor that has a total fuel salt volume of 18 m3 with a mean fuel temperature of 750 °C. The core's shape is a compact cylinder with a height to diameter ratio of 1 where liquid fluoride fuel salt flows from the bottom to the top. The return circulation of the salt, from top to bottom, is broken up into 16 groups of pumps and heat exchangers located around the core. The fuel salt takes approximately 3 to 4 seconds to complete a full cycle. At any given time during operation, half of the total fuel salt volume is in the core and the rest is in the external fuel circuit (salt collectors, salt-bubble separators, fuel heat exchangers, pumps, salt injectors and pipes). MSFRs contain an emergency draining system that is triggered and achieved by redundant and reliable devices such as detection and opening technology. During operation, the fuel salt circulation speed can be adjusted by controlling the power of the pumps in each sector. The intermediate fluid circulation speed can be adjusted by controlling the power of the intermediate circuit pumps. The temperature of the intermediate fluid in the intermediate exchangers can be managed through the use of a double bypass. This allows the temperature of the intermediate fluid at the conversion exchanger inlet to be held constant while its temperature is increased in a controlled way at the inlet of the intermediate exchangers. The temperature of the core can be adjusted by varying the proportion of bubbles injected in the core since it reduces the salt density. As a result, it reduces the mean temperature of the fuel salt. Usually the fuel salt temperature can be brought down by 100 °C using a 3% proportion of bubbles. MSFRs have two draining modes, controlled routine draining and emergency draining. During controlled routine draining, fuel salt is transferred to actively cooled storage tanks. The fuel temperature can be lowered before draining, this may slow down the process. This type of draining could be done every 1 to 5 years when the sectors are replaced. Emergency draining is done when an irregularity occurs during operation. The fuel salt can be drained directly into the emergency draining tank either by active devices or by passive means. The draining must be fast to limit the fuel salt heating in a loss of heat removal event.

Fluoride salt-cooled high-temperature reactor
The fluoride salt-cooled high-temperature reactor (FHR), also called advanced high temperature reactor (AHTR), is also a proposed Generation IV molten-salt reactor variant regarded promising for the long-term future. The FHR/AHTR reactor uses a solid-fuel system along with a molten fluoride salt as coolant.

One version of the Very-high-temperature reactor (VHTR) under study was the liquid-salt very-high-temperature reactor (LS-VHTR). It uses liquid salt as a coolant in the primary loop, rather than a single helium loop. It relies on "TRISO" fuel dispersed in graphite. Early AHTR research focused on graphite in the form of graphite rods that would be inserted in hexagonal moderating graphite blocks, but current studies focus primarily on pebble-type fuel. The LS-VHTR can work at very high temperatures (the boiling point of most molten salt candidates is >1400 °C); low-pressure cooling that can be used to match hydrogen production facility conditions (most thermochemical cycles require temperatures in excess of 750 °C); better electric conversion efficiency than a helium-cooled VHTR operating in similar conditions; passive safety systems and better retention of fission products in the event of an accident.

Liquid-fluoride thorium reactor
Reactors containing molten thorium salt, called liquid fluoride thorium reactors (LFTR), would tap the thorium fuel cycle. Private companies from Japan, Russia, Australia and the United States, and the Chinese government, have expressed interest in developing this technology.

Advocates estimate that five hundred metric tons of thorium could supply U.S. energy needs for one year. The U.S. Geological Survey estimates that the largest-known U.S. thorium deposit, the Lemhi Pass district on the Montana-Idaho border, contains thorium reserves of 64,000 metric tons.

Traditionally, these reactors were known as molten salt breeder reactors (MSBRs) or thorium molten-salt reactors (TMSRs), but the name LFTR was promoted as a rebrand in the early 2000s by Kirk Sorensen.

Stable-salt reactor
The stable salt reactor is a relatively recent concept which holds the molten salt fuel statically in traditional LWR fuel pins. Pumping of the fuel salt, and all the corrosion/deposition/maintenance/containment issues arising from circulating a highly radioactive, hot and chemically complex fluid, are no longer required. The fuel pins are immersed in a separate, non-fissionable fluoride salt which acts as primary coolant.

Dual-fluid molten-salt reactors
A prototypical example of a dual fluid reactor is the lead-cooled, salt-fueled reactor.

Aircraft Reactor Experiment, US


MSR research started with the U.S. Aircraft Reactor Experiment (ARE) in support of the U.S. Aircraft Nuclear Propulsion program. ARE was a 2.5 MWth nuclear reactor experiment designed to attain a high energy density for use as an engine in a nuclear-powered bomber.

The project included experiments, including high temperature and engine tests collectively called the Heat Transfer Reactor Experiments: HTRE-1, HTRE-2 and HTRE-3 at the National Reactor Test Station (now Idaho National Laboratory) as well as an experimental high-temperature molten-salt reactor at Oak Ridge National Laboratory – the ARE.

ARE used molten fluoride salt NaF/ZrF4/UF4 (53-41-6 mol%) as fuel, moderated by beryllium oxide (BeO). Liquid sodium was a secondary coolant.

The experiment had a peak temperature of 860 °C. It produced 100 MWh over nine days in 1954. This experiment used Inconel 600 alloy for the metal structure and piping.

An MSR was operated at the Critical Experiments Facility of the Oak Ridge National Laboratory in 1957. It was part of the circulating-fuel reactor program of the Pratt & Whitney Aircraft Company (PWAC). This was called Pratt and Whitney Aircraft Reactor-1 (PWAR-1). The experiment was run for a few weeks and at essentially zero power, although it reached criticality. The operating temperature was held constant at approximately 675 C. The PWAR-1 used NaF/ZrF4/UF4 as the primary fuel and coolant. It was one of three critical MSRs ever built.

MSRE at Oak Ridge, US


Oak Ridge National Laboratory (ORNL) took the lead in researching MSRs through the 1960s. Much of their work culminated with the Molten-Salt Reactor Experiment (MSRE). MSRE was a 7.4 MWth test reactor simulating the neutronic "kernel" of a type of epithermal thorium molten salt breeder reactor called the liquid fluoride thorium reactor (LFTR). The large (expensive) breeding blanket of thorium salt was omitted in favor of neutron measurements.

MSRE's piping, core vat and structural components were made from Hastelloy-N, moderated by pyrolytic graphite. It went critical in 1965 and ran for four years. Its fuel was LiF/BeF2/ZrF4/UF4 (65-29-5-1)mol%. The graphite core moderated it. Its secondary coolant was FLiBe (2LiF*BeF2). It reached temperatures as high as 650 C and achieved the equivalent of about 1.5 years of full power operation.

Molten salt breeder reactor
From 1970 to 1976 ORNL researched during the 1970–1976 a molten salt breeder reactor (MSBR) design. Fuel was to be LiF/BeF2/ThF4/UF4 (72-16-12-0.4) mol% with graphite moderator. The secondary coolant was to be NaF/Na[BF4]. Its peak operating temperature was to be 705 C. It would follow a 4-year replacement schedule. The MSR program closed down in the early 1970s in favor of the liquid metal fast-breeder reactor (LMFBR), after which research stagnated in the United States. , ARE and MSRE remained the only molten-salt reactors ever operated.

The MSBR project received funding from 1968 to 1976 of (in dollars) $.

Officially, the program was cancelled because:
 * The political and technical support for the program in the United States was too thin geographically. Within the United States the technology was well understood only in Oak Ridge.
 * The MSR program was in competition with the fast breeder program at the time, which got an early start and had copious government development funds with contracts that benefited many parts of the country. When the MSR development program had progressed far enough to justify an expanded program leading to commercial development, the United States Atomic Energy Commission (AEC) could not justify the diversion of substantial funds from the LMFBR to a competing program.

Denatured molten-salt reactor
The denatured molten-salt reactor (DMSR) was an Oak Ridge theoretical design that was never built.

Engel et al. 1980 said the project "examine[ the conceptual feasibility of a molten-salt power reactor fueled with denatured uranium-235 (i.e. with low-enriched uranium) and operated with a minimum of chemical processing." The main design priority was proliferation resistance. Although the DMSR can theoretically be fueled partially by thorium or plutonium, fueling solely with low enriched uranium (LEU) helps maximize proliferation resistance.

Other goals of the DMSR were to minimize research and development and to maximize feasibility. The Generation IV international Forum (GIF) includes "salt processing" as a technology gap for molten-salt reactors. The DMSR design theoretically requires minimal chemical processing because it is a burner rather than a breeder.

United Kingdom
The UK's Atomic Energy Research Establishment (AERE) was developing an alternative MSR design across its National Laboratories at Harwell, Culham, Risley and Winfrith. AERE opted to focus on a lead-cooled 2.5 GWe Molten Salt Fast Reactor (MSFR) concept using a chloride. They also researched helium gas as a coolant.

The UK MSFR would have been fuelled by plutonium, a fuel considered to be 'free' by the program's research scientists, because of the UK's plutonium stockpile.

Despite their different designs, ORNL and AERE maintained contact during this period with information exchange and expert visits. Theoretical work on the concept was conducted between 1964 and 1966, while experimental work was ongoing between 1968 and 1973. The program received annual government funding of around £100,000–£200,000 (equivalent to £2m–£3m in 2005). This funding came to an end in 1974, partly due to the success of the Prototype Fast Reactor at Dounreay which was considered a priority for funding as it went critical in the same year.

Soviet Union
In the USSR, a molten-salt reactor research program was started in the second half of the 1970s at the Kurchatov Institute. It included theoretical and experimental studies, particularly the investigation of mechanical, corrosion and radiation properties of the molten salt container materials. The main findings supported the conclusion that no physical nor technological obstacles prevented the practical implementation of MSRs.

Twenty-first century
MSR interest resumed in the new millennium due to continuing delays in fusion power and other nuclear power programs and increasing demand for energy sources that would incur minimal greenhouse gas (GHG) emissions.

Canada
Terrestrial Energy, a Canadian-based company, is developing a DMSR design called the Integral Molten-Salt Reactor (IMSR). The IMSR is designed to be deployable as a small modular reactor (SMR). Their design currently undergoing licensing is 400MW thermal (190MW electrical). With high operating temperatures, the IMSR has applications in industrial heat markets as well as traditional power markets. The main design features include neutron moderation from graphite, fueling with low-enriched uranium and a compact and replaceable Core-unit. Decay heat is removed passively using nitrogen (with air as an emergency alternative). The latter feature permits the operational simplicity necessary for industrial deployment.

Terrestrial completed the first phase of a prelicensing review by the Canadian Nuclear Safety Commission in 2017, which provided a regulatory opinion that the design features are generally safe enough to eventually obtain a license to construct the reactor.

Moltex Energy Canada, a subsidiary of UK-based Moltex Energy Ltd, has obtained support from New Brunswick Power for the development of a pilot plant in Point Lepreau, Canada, and financial backing from IDOM (an international engineering firm) and is currently engaged in the Canadian Vendor Design Review process. The plant will employ the waste-burning version of the company's stable salt reactor design.

China
China initiated a thorium research project in January 2011, and spent about 3 billion yuan (US$500 million) on it by 2021. A 100 MW demonstrator of the solid fuel version (TMSR-SF), based on pebble bed technology, was planned to be ready by 2024. A 10 MW pilot and a larger demonstrator of the liquid fuel (TMSR-LF) variant were targeted for 2024 and 2035, respectively. China then accelerated its program to build two 12 MW reactors underground at Wuwei research facilities by 2020, beginning with the 2 megawatt TMSR-LF1 prototype. The project sought to test new corrosion-resistant materials. In 2017, ANSTO/Shanghai Institute Of Applied Physics announced the creation of a NiMo-SiC alloy for use in MSRs.

In 2021, China stated that Wuwei prototype operation could start power generation from thorium in September, with a prototype providing energy for around 1,000 homes. It is the world's first nuclear molten-salt reactor after the Oak Ridge project. The 100 MW successor was expected to be 3 meters tall and 2.5 meters wide, capable of providing energy to 100,000 homes.

Further work on commercial reactors was announced with the target completion date of 2030. Chinese government plans to realize similar reactors in deserts and plains of western China as well as up to 30 in countries involved in China's "Belt and Road" initiative.

In 2022, Shanghai Institute of Applied Physics (SINAP) was given approval by the Ministry of Ecology and Environment to commission an experimental thorium-powered MSR.

Denmark
Copenhagen Atomics is a Danish molten salt technology company developing mass manufacturable molten salt reactors. The Copenhagen Atomics Waste Burner is a single-fluid, heavy water moderated, fluoride-based, thermal spectrum and autonomously controlled molten-salt reactor. This is designed to fit inside of a leak-tight, 40-foot, stainless steel shipping container. The heavy water moderator is thermally insulated from the salt and continuously drained and cooled to below 50 C. A molten lithium-7 deuteroxide moderator version is also being researched. The reactor utilizes the thorium fuel cycle using separated plutonium from spent nuclear fuel as the initial fissile load for the first generation of reactors, eventually transitioning to a thorium breeder. Copenhagen Atomics is actively developing and testing valves, pumps, heat exchangers, measurement systems, salt chemistry and purification systems, and control systems and software for molten salt applications.

Seaborg Technologies is developing the core for a compact molten-salt reactor (CMSR). The CMSR is a high temperature, single salt, thermal MSR designed to go critical on commercially available low enriched uranium. The CMSR design is modular, and uses proprietary NaOH moderator. The reactor core is estimated to be replaced every 12 years. During operation, the fuel will not be replaced and will burn for the entire 12-year reactor lifetime. The first version of the Seaborg core is planned to produce 250 MWth power and 100 MWe power. As a power plant, the CMSR will be able to deliver electricity, clean water and heating/cooling to around 200,000 households.

France
The CNRS project EVOL (Evaluation and viability of liquid fuel fast reactor system) project, with the objective of proposing a design of the molten salt fast reactor (MSFR), released its final report in 2014. Various MSR projects like FHR, MOSART, MSFR, and TMSR have common research and development themes.

The EVOL project will be continued by the EU-funded Safety Assessment of the Molten Salt Fast Reactor (SAMOFAR) project, in which several European research institutes and universities collaborate.

Germany
The German Institute for Solid State Nuclear Physics in Berlin has proposed the dual fluid reactor as a concept for a fast breeder lead-cooled MSR. The original MSR concept used the fluid salt to provide the fission materials and also to remove the heat. Thus it had problems with the needed flow speed. Using 2 different fluids in separate circles is thought to solve the problem.

India
In 2015, Indian researchers published a MSR design, as an alternative path to thorium-based reactors, according to India's three-stage nuclear power programme.

Indonesia
Thorcon is developing the TMSR-500 molten-salt reactor for the Indonesian market. National Research and Innovation Agency, through its Research Organization for Nuclear Energy announced its renewal of interest on MSR reactor research on 29 March 2022 and planned to study and develop MSR for thorium-fueled nuclear reactors.

Japan
The Fuji Molten-Salt Reactor is a 100 to 200 MWe LFTR, using technology similar to the Oak Ridge project. A consortium including members from Japan, the U.S. and Russia are developing the project. The project would likely take 20 years to develop a full size reactor, but the project seems to lack funding.

Russia
In 2020, Rosatom announced plans to build a 10 MWth FLiBe burner MSR. It would be fueled by plutonium from reprocessed VVER spent nuclear fuel and fluorides of minor actinides. It is expected to launch in 2031 at Mining and Chemical Combine.

United Kingdom
The Alvin Weinberg Foundation is a British non-profit organization founded in 2011, dedicated to raising awareness about the potential of thorium energy and LFTR. It was formally launched at the House of Lords on 8 September 2011. It is named after American nuclear physicist Alvin M. Weinberg, who pioneered thorium MSR research.

Moltex Energy's stable-salt reactor design was selected as the most suitable of six MSR designs for UK implementation in a 2015 study commissioned by the UK's innovation agency, Innovate UK. UK government support has been weak, but the company's UK arm, MoltexFLEX, launched its FLEX small modular design in October 2022.

United States
Idaho National Laboratory designed a molten-salt-cooled, molten-salt-fuelled reactor with a prospective output of 1000 MWe.

Kirk Sorensen, former NASA scientist and chief nuclear technologist at Teledyne Brown Engineering, is a long-time promoter of the thorium fuel cycle, coining the term liquid fluoride thorium reactor. In 2011, Sorensen founded Flibe Energy, a company aimed at developing 20–50 MW LFTR reactor designs to power military bases. (It is easier to approve novel military designs than civilian power station designs in the US nuclear regulatory environment).

Transatomic Power pursued what it termed a waste-annihilating molten-salt reactor (WAMSR), intended to consume existing spent nuclear fuel, from 2011 until ceasing operation in 2018 and open-sourcing their research.

In January 2016, the United States Department of Energy announced a $80m award fund to develop Generation IV reactor designs. One of the two beneficiaries, Southern Company will use the funding to develop a molten chloride fast reactor (MCFR), a type of MSR developed earlier by British scientists.

In 2021, Tennessee Valley Authority (TVA) and Kairos Power announced a TRISO-fueled, low-pressure fluoride salt-cooled 140 MWe test reactor to be built in Oak Ridge, Tennessee. A construction permit for the project was issued by the US Nuclear Regulatory Commission (NCR) in 2023. The design is expected to operate at 45% efficiency. The outlet temperature is 650 C. The main steam pressure is 19 MPa. The reactor structure is 316 stainless steel. The fuel is enriched to 19.75%. Loss-of-power cooling is passive. In February 2024 DOE and Kairos Power signed a $303M Technology Investment Agreement to support the design, construction, and commissioning of the reactor. The company is to receive fixed payments upon completing project milestones.

Also in 2021, Southern Company, in collaboration with TerraPower and the U.S. Department of Energy announced plans to build the Molten Chloride Reactor Experiment, the first fast-spectrum salt reactor at the Idaho National Laboratory.

Abilene Christian University (ACU) has applied to the NRC for a construction licence for a 1MWt molten-salt research reactor (MSRR), to be built on its campus in Abilene, Texas, as part of the Nuclear Energy eXperimental Testing (NEXT) laboratory. ACU plans for the MSRR to achieve criticality by December 2025.