{"id":24072,"date":"2023-03-14T19:29:33","date_gmt":"2023-03-14T19:29:33","guid":{"rendered":"https:\/\/rpmanetworks.com\/AtomkraftCloneSite\/?post_type=docs&amp;p=24072"},"modified":"2023-03-14T19:29:33","modified_gmt":"2023-03-14T19:29:33","password":"","slug":"smeltesalt-reaktor-msr","status":"publish","type":"docs","link":"https:\/\/rpmanetworks.com\/atomkraftclonesite-english\/docs\/smeltesalt-reaktor-msr\/","title":{"rendered":"Molten Salt Reactor (MSR)"},"content":{"rendered":"\n<p><strong>What is MSR?<\/strong><font _mstmutation=\"1\"><\/font><\/p>\n\n\n\n<figure class=\"wp-block-image alignright size-full is-resized\"><img fetchpriority=\"high\" decoding=\"async\" src=\"https:\/\/rpmanetworks.com\/AtomkraftCloneSite\/wp-content\/uploads\/2023\/05\/image-17.png\" alt=\"\" class=\"wp-image-25737\" width=\"469\" height=\"332\"\/><\/figure>\n\n\n\n<p>MSR, or Molten Salt Reactor, is a type of nuclear power reactor that operates on the same principles as current reactors. It uses controlled fission to generate steam, which drives electric turbines. However, unlike traditional reactors, the primary coolant used in MSR is a salt heated above its melting point, resulting in a liquid known as molten salt.<\/p>\n\n\n\n<p>MSR is one of the Generation 4 (Gen IV) nuclear reactor designs currently being developed. This innovative technology can potentially revolutionize how we generate electricity, as it offers several advantages over traditional nuclear reactors.<\/p>\n\n\n\n<p>For one, using molten salt as a coolant makes the reactor much safer, as it has a higher boiling point than water and is less likely to evaporate and cause a meltdown. Additionally, the molten salt can be used to store heat, which means the reactor can continue generating electricity even when it is not actively producing steam.<\/p>\n\n\n\n<p>Overall, MSR is an exciting development in nuclear energy, and it has the potential to provide a safe, reliable, and sustainable source of electricity for generations to come.<\/p>\n\n\n\n<p><strong>Is MSR scientifically proven?<\/strong><\/p>\n\n\n\n<p>The molten salt reactor (MSR) is based on a proven concept in the experimental phase. The United States Oak Ridge National Laboratories created a small 8-megawatt experimental molten salt reactor. It ran from 1965 to 1969 [1].<\/p>\n\n\n\n<p><strong>The project was abandoned due to a lack of interest by the US government.<\/strong><\/p>\n\n\n\n<p>High-efficiency MSR reactors can operate at higher temperatures, resulting in significantly higher efficiency.<\/p>\n\n\n\n<p>MSR can be used as a &#8220;burner reactor,&#8221; meaning it can use fuel from other reactors, such as light water reactors.<\/p>\n\n\n\n<p><strong>Benefits of Molten Salt Reactors<\/strong><\/p>\n\n\n\n<p>The benefits of MSRs are plentiful, hence their resilience as an interesting topic throughout reactor history. We break them down by topic here.<\/p>\n\n\n\n<p><\/p>\n\n\n\n<h3 class=\"wp-block-heading\">Sustainability<\/h3>\n\n\n\n<p>Sustainability is a measure of how efficiently a system can use natural resources. Most traditional reactors can only burn about 1% of the uranium on Earth. Many advanced reactors, including MSRs, can do much better. Here\u2019s why MSRs are good in this regard.<\/p>\n\n\n\n<ul class=\"wp-block-list\">\n<li><strong>Online fission product removal<\/strong>&nbsp;\u2014 Since the fuel is liquid, it can be processed during operation. This means that when atoms split into smaller atoms (fission products), those small atoms can be collected and pulled out of the core very quickly. This prevents those atoms from absorbing neutrons that would otherwise continue the chain reaction. This allows very high fuel efficiency in MSRs.<\/li>\n\n\n\n<li><font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Good utilization of&nbsp;<a href=\"https:\/\/whatisnuclear.com\/thorium.html\">Thorium<\/a><\/strong>&nbsp;\u2014 As mentioned above, the MSR chemical plant can continuously remove fission products and other actinides during operation. This means that when Thorium absorbs a neutron and becomes Pa-233, the Protactinium can be removed from the core and allowed to decay to U-233 in peace, without any risk of causing parasitic neutron losses. While this is not the only way to burn Thorium, it is perhaps the most elegant.<\/li>\n\n\n\n<li><font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>No neutron losses in structure<\/strong>&nbsp;\u2014 Since there is no structure like cladding, fuel ducts, grid spacers, etc., there are no neutron losses in these. This helps fuel efficiency and therefore sustainability.<\/li>\n<\/ul>\n\n\n\n<p><\/p>\n\n\n\n<h3 class=\"wp-block-heading\">Economics<\/h3>\n\n\n\n<p>Though economics is not truly known until a system is in commercial operation, there are reasons to think MSRs would have favorable low prices.<font _mstmutation=\"1\"><\/font><\/p>\n\n\n\n<ul class=\"wp-block-list\">\n<li><strong>Online refueling<\/strong>\u00a0\u2014 Where normal reactors have to shut down to move fuel around or put new fuel in, MSRs can do all this while at full power. You just dump in a new chunk of fuel into the vat (carefully, of course). This allows high capacity factors, improving economics. The reactors may still have to shut down to do maintenance, but they likely will have better uptimes.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>No fuel fabrication<\/strong>\u00a0\u2014 Any commercial fuel fabricator will tell you that it is expensive to build fuel assemblies, fuel pellets, cladding tubes, core support structures, flow orifices, etc. MSRs are basically just vats of fuel, so they are much simpler and cheaper in this regard.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>High temperatures possible<\/strong>\u00a0\u2014 Molten salts were first looked at for their ability to go to very high temperatures. At high temperatures, power cycles convert heat to electricity with much less loss, giving you more money for a given amount of heat. Additionally, many industrial processes require high-grade heat, and these reactors could be used to that while producing electricity. Best of all, MSRs can do high temperatures without a pressurized coolant (as required in gas-cooled reactors).<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Smaller containment<\/strong>&nbsp;\u2014 Since the system pressure is low and the heat capacity is high, the containments can be smaller and thinner.<\/li>\n<\/ul>\n\n\n\n<p><strong>Safety<\/strong><\/p>\n\n\n\n<p>The most important aspect of a nuclear reactor is safety. Here&#8217;s the good news for MSRs:<font _mstmutation=\"1\"><\/font><\/p>\n\n\n\n<ul class=\"wp-block-list\">\n<li><strong>Very low excess reactivity<\/strong>\u00a0\u2014 Since they can be continually refueled, there is no need to load extra fissile material to allow the reactor to operate for a long time. This means that it is difficult to have something happen (like an earthquake) that could cause a shift in geometry that inserts reactivity and causes a power spike.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Negative temperature coefficient of reactivity<\/strong>\u00a0\u2014 In general, if the fuel heats up, it expands and becomes less reactive, keeping things stable. Note that this is not always true in graphite-moderated MSRs.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong _istranslated=\"1\">Low<\/strong> <strong>pressure<\/strong> \u2014 Since the fuel and coolant are at atmospheric pressure, a leak in a tube doesn&#8217;t automatically result in the expulsion of a bunch of fuel and coolant. This is a major safety advantage that enables passive decay heat removal (preventing things like what happened at Fukushima). The salts generally have extremely high heat capacity as well, so they can absorb a lot of heat themselves. On the other hand, their thermal conductivity is about 60x worse than liquid metal sodium.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong _istranslated=\"1\">No chemical reactivity with air or water<\/strong> \u2014 The fuel salt is generally not violently reactive to the environment. So where LWRs have hydrogen explosions and SFRs have sodium fires, MSRs do well. Of course, MSR leaks are still serious because it&#8217;s not just coolant&#8230; it&#8217;s extremely radioactive fuel.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Drain tank failure mechanism<\/strong>&nbsp;\u2014 If something goes wrong in an MSR and the temperature starts going up, a freeze plug can melt, pouring the entire core into subcritical drain tanks that are intimately linked to an ultimate heat sink, keeping them cool. This is an interesting accident mitigation feature that is possible only in fluid fuel reactors. Since freeze plugs can take some time to actuate, faster mechanisms have also been proposed.<\/li>\n<\/ul>\n\n\n\n<p><strong>Problems with Molten Salt Reactors<\/strong><\/p>\n\n\n\n<p>All those wonderful benefits can&#8217;t possibly come without a slew of problems. Lots of people promote these reactors without acknowledging the issues, but not us! A reactor concept has to stand on two feet even in the face of disadvantages (and we think the MSR can do this). Let&#8217;s go through them.<\/p>\n\n\n\n<p><strong>Mobile fission products<\/strong><\/p>\n\n\n\n<p>The primary concern with MSRs is that the radioactive fission products can get everywhere. They are not in fuel pins surrounded by cladding but are just in a big, sealed vat. You can put a double-layer containment around it, sure, but it is still challenging to keep them all accounted for. Where some of these fission products and actinides are radioactive, others have chemical effects that can eat away at the containment. The implications of this are many.<\/p>\n\n\n\n<ul class=\"wp-block-list\">\n<li><strong>Material Degradation<\/strong>\u00a0\u2014 with half the periodic table of the elements dissolved in salt and in contact with the containment vessel, there are lots of corrosion and related concerns. Noble metals will naturally plate out on cold metal surfaces. In a power reactor, a heat exchanger will be the coldest metal around, and so the heat transfer surfaces will need periodic replacement. At MSRE, Tellurium caused cracking of the Hastelloy-N material. This was mitigated with chemistry, but similar problems may show up in long-lived power reactors.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Tritium production<\/strong>\u00a0If lithium is used in the salt, tritium will be produced, which is radioactive and extremely mobile (since it is small, it can go through metal like a hot knife through butter). ORNL used a special sodium fluoroborate intermediate salt to capture most of it, but a large amount still escaped to the environment.<font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Remote maintenance<\/strong>\u00a0The chemical plants will need periodic maintenance, but all of the equipment will be highly radioactive. Expensive remote maintenance will be required. If a graphite moderator is used, its replacement will also be remote and expensive.<\/li>\n\n\n\n<li><strong _istranslated=\"1\">Complex chemical plant<\/strong> \u2014 Some of the fission product removals is simple, such as the gas sparging to remove Xe and Kr, and noble metal plateout. But to do the more serious fission product (or actinide) separation, complex processes are required, such as the liquid Bismuth reductive process, volatilization, or electroplating<font _mstmutation=\"1\" _msttexthash=\"106338128\" _msthash=\"2249\">. These have been studied in detail, but are complex enough to be a disadvantage. Don&#8217;t make us post a process flow diagram. (You can find one from the MSBR on page 8 of <\/font><a _istranslated=\"1\" href=\"http:\/\/www.osti.gov\/scitech\/biblio\/6650305\">ORNL-TM-6413<\/a>.)<\/li>\n<\/ul>\n\n\n\n<p><\/p>\n\n\n\n<h3 class=\"wp-block-heading\">Proliferation<\/h3>\n\n\n\n<p>The main political barrier to MSRs is their perceived bomb-factory capabilities. If you talk to&nbsp;<a href=\"https:\/\/whatisnuclear.com\/non-proliferation.html\">non-proliferation people<\/a>, they will tell you that as soon as the (solid) fuel pins are cut open, a technology is considered proliferative. The problem with MSRs, then, is that the fuel is already completely cut open and melted. You\u2019re halfway to a bomb already, they think. Here\u2019s what they are worried about.<\/p>\n\n\n\n<ul class=\"wp-block-list\">\n<li><font _mstmutation=\"1\" _msttexthash=\"444407249\" _msthash=\"2329\"><strong _istranslated=\"1\" _mstmutation=\"1\">Protactinium-233 decays to pure, weapons-grade<\/strong> U-233 \u2014 Many Thorium-cycle MSRs have to capture Pa as it is produced, removing it from the system while it decays to U-233 and then reinserting it into the reactor. They have to do this because otherwise, the Pa-233 absorbs too many neutrons to maintain a breeding cycle. The problem here is that that ex-core U-233 is basically pure weapons-grade U-233 which could be used to make a bomb. It usually comes with Zr, but separating Pa from Zr is simple. Not many common reactors require such a proliferative step in their fuel cycle. Many MSR concepts do not do this, but MSBRs (like the LFTR) require it. Therefore, the owner of an MSBR<font _mstmutation=\"1\" _msttexthash=\"396980558\" _msthash=\"2306\"> could be producing bombs on the side. Many of the ideas for mitigating this problem (such as U-232 contamination and denaturing) only help against diversion by a nefarious third party. The owners of the plant could side-step these kinds of fixes easily, and that&#8217;s really what matters.<\/font><\/font><font _mstmutation=\"1\"><\/font><\/li>\n\n\n\n<li><strong>Inventory tracking is difficult<\/strong>&nbsp;&#8212; Because a lot of materials plate out in the reactor and in the chemical plant, it is difficult to keep exact track of all of your actinides. The IAEA puts safeguards in reactors to make sure that all the actinides are accounted for (to verify that no one\u2019s making bombs on the side) but it will be difficult for the IAEA to distinguish plate-out losses from actual proliferative losses.<\/li>\n<\/ul>\n\n\n\n<p><strong>Other minor issues<\/strong><\/p>\n\n\n\n<h4 class=\"wp-block-heading\" id=\"other-minor-issues\">There are a few other concerns, but these probably have practical solutions.<\/h4>\n\n\n\n<ul class=\"wp-block-list\">\n<li><strong>Unknown waste form<\/strong>&nbsp;\u2014 It\u2019s not clear what nuclear waste from MSRs will look like. The salt itself is not contained enough to be put in a repository so someone will have to come up with a stable waste form.<\/li>\n\n\n\n<li><strong>Electrical heaters are required to stay liquid<\/strong>&nbsp;\u2014 in a prolonged power outage, the colder parts of the heat transfer loop might solidify. This could cause temperatures to rise over in the core (which will of course still be self-heated liquid).<\/li>\n\n\n\n<li><strong>Flowing delayed neutron precursors<\/strong>&nbsp;\u2014 since the fuel flows, the fission products that generate delayed neutrons are swept out of and then back into the core. The dynamics of this are unconventional and can lead to reactivity increases when the pump stops.<\/li>\n<\/ul>\n\n\n\n<p><strong>Exotics in the salt<\/strong><\/p>\n\n\n\n<p>For MSRs to breed with slow neutrons, the lithium in the salt must be enriched to very pure Li-7. Li-6 is a strong neutron poison and becomes tritium, the pesky mobile radiation source. Also, Beryllium in Flibe is a controlled substance. It has some weapons applications and is a very dangerous material in terms of biological inhalation risks. In chloride salts, you must enrich to have pure Cl-37. Otherwise, Cl-35 has a strong (n,proton) threshold reaction that poisons the reactor. Also, the activation product Cl-36 is a long-lived, water soluble, hard beta emitter that complicates waste disposal. These enrichment needs increase the cost and complexity of MSR fuel cycles. Maybe we can find a more ideal salt someday.<\/p>\n\n\n\n<p><strong>History of Molten Salt Reactors<\/strong><\/p>\n\n\n\n<p>The first fluid fueled reactors were built during the Manhattan project. They were Aqueous Homogeneous Reactors (AHR), meaning they were solutions of uranium or plutonium in water. These small reactors were primarily used to study plutonium. Later (concurrently to MSR development), several AHR test reactors were built at Oak Ridge National Laboratory (these were the Homogeneous Reactor Experiments HRE-1 and HRE-2). Molten salt fuels were first conceived of in the late 1940s, when people began thinking of nuclear powered airplanes! The idea was to have very long range bombers in the air at all times. To heat air to high enough temperatures to provide thrust, such a nuclear reactor would need very high temperatures and very high power densities. The Aircraft Nuclear Propulsion program was a huge effort, and most of the early studies of molten salts were done under its direction. The first molten salt reactor, the\u00a0<a href=\"https:\/\/en.wikipedia.org\/wiki\/Aircraft_Reactor_Experiment\">Aircraft Reactor Experiment (ARE)<\/a>\u00a0operated in 1954 at ORNL with a Na-Zr-U salt for 96 MW-hours. This reactor actually had fuel pumping through tubes in blocks of Beryllium. When inter-continental ballistic missiles came along, this program was promptly canceled.<\/p>\n\n\n\n<p>After the cancellation of the ANP project, the people at ORNL wanted to use their MSR skills to build a commercial power plant. In 1956, ORNL director Alvin Weinberg hired a guy named MacPherson to form a group at ORNL to build such a thing. To be successful, they needed a fuel salt that absorbed very few neutrons, dissolved much uranium and thorium, was thermally stable, and was chemically compatible with structural materials. They decided the fluorides were best, but UF<sub>4<\/sub>&nbsp;had a very high melting temperature (1035 C). Mixed with BeF<sub>2<\/sub>, the melting temperature became practical, but the viscosity was too high. Mixing in some LiF brought the viscosity down. Thus was born UF<sub>4<\/sub>-LiF-BeF<sub>2<\/sub>, now known as Flibe. Construction of a test reactor called the Molten Salt Reactor Experiment (MSRE) began in 1962 using this salt (with a bit of ZrF<sub>4<\/sub>), and the plant began operation in 1966. In 1968, all the uranium was extracted and replaced with U-233, the fissile nuclide of the Thorium cycle. Thus, MSRE was the first reactor to operate on U-233. The reactor was shut down on schedule in 1969 as funding was set to go towards designing and building a bigger prototype MSR called the Molten Salt Breeder Reactor (MSBR).<\/p>\n\n\n\n<p>But it would not be so! The Atomic Energy Commission (the ancestor of the Dept. of Energy) could not be convinced to put more money into the molten salt project. For one thing, they were already over budget on a very large and expensive&nbsp;<a href=\"https:\/\/whatisnuclear.com\/fast-reactor.html\">fast-breeder<\/a>&nbsp;project. Besides, there were some big problems at MSRE that some people were not convinced could be solved. ORNL director Alvin Weinberg put much energy into keeping the program going, but it was not destined to be. Funding was largely canceled and MSRs lost their momentum.<\/p>\n\n\n\n<p>MSR work continued at a low budget. The ORNL experts came up with likely solutions to most of the problems raised at the MSRE. When proliferation concerns about the MSR were brought up in the 1980s, ORNL developed (on paper) something called the denatured MSR, or DMSR that was not fissile self-sufficient, but still offered favorable performance in comparison to traditional reactors. Others throughout the world worked on salt chemistry problems and developed many other designs, including some chloride salt fast breeder MSRs. Much later, in 2001, the MSR was chosen by the Generation IV forum as one of the 6 Gen-IV concepts. This jump-started work on MSRs and engineers and chemists have produced much good work on them since then.<\/p>\n\n\n\n<p><strong>Salt-cooled reactors<\/strong><\/p>\n\n\n\n<p>The step-sister reactor of the MSR is the fluoride cooled high temperature reactor (FHR). These reactors have solid fuel in the form of TRISO particles (like the high temperature gas-cooled reactor), but rather than pumping high-pressure helium coolant through, they pump low-pressure liquid salt (usually Flibe) through. The idea here is to get the high-temperature and high-burnup benefits of the gas reactors without the risk of a depressurization accident. Salt coolant has incredible heat capacity (but low thermal conductivity), so it does a good job of handling accidents. These reactors are currently being studied by the DOE and many others (including the Chinese).\u00a0<a href=\"https:\/\/whatisnuclear.com\/assets\/FHR_Project_Presentation_January_2012a.pdf\">Here is a PDF<\/a>\u00a0presentation by one of the PIs at MIT.<\/p>\n\n\n\n<p><strong>Ongoing Molten Salt Reactor Work<\/strong><\/p>\n\n\n\n<p>There is ongoing work in MSRs around the world. The Europeans are working on MOSART, the Japanese have FUJI, the Americans are focused on the FHR. In 2011, the Chinese Academy of Science started a project in Shanghai to put substantial resources into MSR technology. There are 300-500 people on the project, with a budget in the hundreds of millions. Most of the work is on FHRs, but there is definitely MSR work as well. They are manufacturing Hastelloy-N, separating lithium, building salt loops, and building advanced modeling capabilities. That project is most likely the most exciting in MSRs since 1969. They plan on having both an experimental 2MW FHR and an experimental 2MW MSR operational by 2020.<\/p>\n\n\n\n<p>Several start-up companies have emerged to commercialize molten salt reactors. In Canada,\u00a0<a href=\"https:\/\/terrestrialenergy.com\/\">Terrestrial Energy<\/a>\u00a0is working on small modular MSRs, featuring small reactor vessels that can be swapped out of a plant every 7 years or so.\u00a0<a href=\"http:\/\/thorconpower.com\/\">ThorCon<\/a>\u00a0is using its extensive experience in the ship-building industry to develop MSRs that need no new technology and can be built in the very near term. In Alabama, Kirk Sorensen himself runs a company called\u00a0<a href=\"http:\/\/flibe-energy.com\/\">Flibe Energy<\/a>\u00a0targeting the development of small modular Thorium-MSRs. These companies represent the modern revival of interest in MSRs and we wish them all the best!<\/p>\n\n\n\n<p><\/p>\n\n\n\n<h3 class=\"wp-block-heading\">Summary<\/h3>\n\n\n\n<p>There are more specific problems with more specific types of MSRs, but you get the general idea here. Basically, MSRs are underdeveloped and require a lot more research (especially in corrosion) before they can surely take off as the world\u2019s fleet of power plants. Personally, we think (as did Alvin Weinberg and Edward Teller) that these reactors have a shining place in the mid-future. Right now, we have to keep studying them! Fortunately, much work is ongoing.<\/p>\n\n\n\n<p><strong>Sources <\/strong><\/p>\n\n\n\n<ol class=\"wp-block-list\">\n<li><a href=\"https:\/\/www.ornl.gov\/blog\/ornl-review\/look-back-molten-salt-reactor-experiment?fbclid=IwAR1s7K_xRLQY8WW8PHiCj0_G75bvpH6suTZGRxaZp-yGPCLzxDUS-hwLY7k\">https:\/\/www.ornl.gov\/blog\/ornl-review\/look-back-molten-salt-reactor-experiment?fbclid=IwAR1s7K_xRLQY8WW8PHiCj0_G75bvpH6suTZGRxaZp-yGPCLzxDUS-hwLY7k<\/a><\/li>\n\n\n\n<li><a href=\"https:\/\/whatisnuclear.com\/msr.html\">Molten salt reactors (whatisnuclear.com)<\/a><\/li>\n\n\n\n<li><a href=\"https:\/\/www.osti.gov\/biblio\/4227904\">Program plan for development of molten-salt breeder reactors (ORNL-5018)&nbsp;<\/a>\u2014 This 1974 reference is what the world\u2019s preeminent molten-salt scientists wrote to future reactor developers about what they had accomplished and how to pick up right where they left off. Above all other molten-salt related references, this one is probably the most useful to anyone working on MSRs. It has detailed lists of what research needs to be done, how long it will probably take, and how much it will cost. It\u2019s a true wonder.<\/li>\n\n\n\n<li><a href=\"https:\/\/www.tandfonline.com\/doi\/abs\/10.13182\/NT70-A28619\">Molten-Salt Reactors\u2014History, Status, and Potential<\/a>&nbsp;\u2014 An excellent discussion of the history of MSRs. Alternate download&nbsp;<a href=\"http:\/\/moltensalt.org\/references\/static\/downloads\/pdf\/NAT_MSRintro.pdf\">here<\/a><\/li>\n\n\n\n<li><a href=\"https:\/\/www.osti.gov\/biblio\/4654707\">MSRE Design and Operations Report, Part I, Description of Reactor Design (ORNL-TM-728)<\/a>&nbsp;\u2014 A description of the Molten Salt Reactor Experiment design. This is part of a 10-part series describing the experience with the MSRE. All documents are widely available.<\/li>\n\n\n\n<li><a href=\"https:\/\/en.wikipedia.org\/wiki\/Aircraft_Reactor_Experiment\">The Aircraft Reactor Experiment<\/a><\/li>\n<\/ol>\n\n\n\n<p><\/p>\n","protected":false},"excerpt":{"rendered":"<p>What is MSR? MSR, or Molten Salt Reactor, is a type of nuclear power reactor that operates on the same principles as current reactors. It uses controlled fission to generate steam, which drives electric turbines. However, unlike traditional reactors, the primary coolant used in MSR is a salt heated above its melting point, resulting in [&hellip;]<\/p>\n","protected":false},"author":1,"featured_media":0,"comment_status":"open","ping_status":"closed","template":"","meta":{"_uag_custom_page_level_css":"","site-sidebar-layout":"default","site-content-layout":"","ast-site-content-layout":"default","site-content-style":"default","site-sidebar-style":"default","ast-global-header-display":"","ast-banner-title-visibility":"","ast-main-header-display":"","ast-hfb-above-header-display":"","ast-hfb-below-header-display":"","ast-hfb-mobile-header-display":"","site-post-title":"","ast-breadcrumbs-content":"","ast-featured-img":"","footer-sml-layout":"","ast-disable-related-posts":"","theme-transparent-header-meta":"","adv-header-id-meta":"","stick-header-meta":"","header-above-stick-meta":"","header-main-stick-meta":"","header-below-stick-meta":"","astra-migrate-meta-layouts":"default","ast-page-background-enabled":"default","ast-page-background-meta":{"desktop":{"background-color":"var(--ast-global-color-4)","background-image":"","background-repeat":"repeat","background-position":"center center","background-size":"auto","background-attachment":"scroll","background-type":"","background-media":"","overlay-type":"","overlay-color":"","overlay-opacity":"","overlay-gradient":""},"tablet":{"background-color":"","background-image":"","background-repeat":"repeat","background-position":"center center","background-size":"auto","background-attachment":"scroll","background-type":"","background-media":"","overlay-type":"","overlay-color":"","overlay-opacity":"","overlay-gradient":""},"mobile":{"background-color":"","background-image":"","background-repeat":"repeat","background-position":"center center","background-size":"auto","background-attachment":"scroll","background-type":"","background-media":"","overlay-type":"","overlay-color":"","overlay-opacity":"","overlay-gradient":""}},"ast-content-background-meta":{"desktop":{"background-color":"var(--ast-global-color-5)","background-image":"","background-repeat":"repeat","background-position":"center center","background-size":"auto","background-attachment":"scroll","background-type":"","background-media":"","overlay-type":"","overlay-color":"","overlay-opacity":"","overlay-gradient":""},"tablet":{"background-color":"var(--ast-global-color-5)","background-image":"","background-repeat":"repeat","background-position":"center center","background-size":"auto","background-attachment":"scroll","background-type":"","background-media":"","overlay-type":"","overlay-color":"","overlay-opacity":"","overlay-gradient":""},"mobile":{"background-color":"var(--ast-global-color-5)","background-image":"","background-repeat":"repeat","background-position":"center center","background-size":"auto","background-attachment":"scroll","background-type":"","background-media":"","overlay-type":"","overlay-color":"","overlay-opacity":"","overlay-gradient":""}},"footnotes":""},"doc_category":[99],"doc_tag":[],"class_list":["post-24072","docs","type-docs","status-publish","hentry","doc_category-reaktor-teknologi"],"year_month":"2026-05","word_count":3216,"total_views":"34","reactions":{"happy":"0","normal":"0","sad":"0"},"author_info":{"name":"admin","author_nicename":"admin","author_url":"https:\/\/rpmanetworks.com\/atomkraftclonesite-english\/author\/admin\/"},"doc_category_info":[{"term_name":"Reactor Technology","term_url":"https:\/\/rpmanetworks.com\/atomkraftclonesite-english\/docs-category\/reaktor-teknologi\/"}],"doc_tag_info":[],"yoast_head":"<!-- This site is optimized with the Yoast SEO plugin v27.6 - https:\/\/yoast.com\/product\/yoast-seo-wordpress\/ -->\n<title>Molten Salt Reactor (MSR) - Foreningen Atomkraft Ja Tak<\/title>\n<meta name=\"robots\" content=\"index, follow, max-snippet:-1, max-image-preview:large, max-video-preview:-1\" \/>\n<link rel=\"canonical\" href=\"https:\/\/rpmanetworks.com\/atomkraftclonesite-english\/docs\/smeltesalt-reaktor-msr\/\" \/>\n<meta property=\"og:locale\" content=\"en_US\" \/>\n<meta property=\"og:type\" content=\"article\" \/>\n<meta property=\"og:title\" content=\"Molten Salt Reactor (MSR) - Foreningen Atomkraft Ja Tak\" \/>\n<meta property=\"og:description\" content=\"What is MSR? 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