GB2511113A - A simple low cost molten salt thorium breeder nuclear reactor - Google Patents
A simple low cost molten salt thorium breeder nuclear reactor Download PDFInfo
- Publication number
- GB2511113A GB2511113A GB1303279.2A GB201303279A GB2511113A GB 2511113 A GB2511113 A GB 2511113A GB 201303279 A GB201303279 A GB 201303279A GB 2511113 A GB2511113 A GB 2511113A
- Authority
- GB
- United Kingdom
- Prior art keywords
- liquid
- nuclear reactor
- tubes
- array
- heat exchanger
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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- 150000003839 salts Chemical class 0.000 title claims abstract description 48
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 title claims abstract description 12
- 229910052776 Thorium Inorganic materials 0.000 title claims abstract description 12
- 239000007788 liquid Substances 0.000 claims abstract description 32
- 229910001338 liquidmetal Inorganic materials 0.000 claims abstract 4
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 14
- 229910052799 carbon Inorganic materials 0.000 claims description 12
- 229910052751 metal Inorganic materials 0.000 claims description 11
- 239000002184 metal Substances 0.000 claims description 11
- PUZPDOWCWNUUKD-UHFFFAOYSA-M sodium fluoride Chemical compound [F-].[Na+] PUZPDOWCWNUUKD-UHFFFAOYSA-M 0.000 claims description 10
- 239000000203 mixture Substances 0.000 claims description 9
- 229910052797 bismuth Inorganic materials 0.000 claims description 7
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 claims description 7
- 239000000835 fiber Substances 0.000 claims description 6
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims description 5
- 229910010271 silicon carbide Inorganic materials 0.000 claims description 5
- 235000013024 sodium fluoride Nutrition 0.000 claims description 5
- 239000011775 sodium fluoride Substances 0.000 claims description 5
- 239000003638 chemical reducing agent Substances 0.000 claims description 4
- 229910052793 cadmium Inorganic materials 0.000 claims description 3
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 claims description 3
- 230000007246 mechanism Effects 0.000 claims description 3
- MZQZQKZKTGRQCG-UHFFFAOYSA-J thorium tetrafluoride Chemical compound F[Th](F)(F)F MZQZQKZKTGRQCG-UHFFFAOYSA-J 0.000 claims description 3
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 claims description 2
- 238000010521 absorption reaction Methods 0.000 claims description 2
- 229910052744 lithium Inorganic materials 0.000 claims description 2
- 150000002739 metals Chemical class 0.000 claims description 2
- 239000007921 spray Substances 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims 1
- 238000001816 cooling Methods 0.000 claims 1
- 229910052708 sodium Inorganic materials 0.000 claims 1
- 239000011734 sodium Substances 0.000 claims 1
- 239000000446 fuel Substances 0.000 abstract description 29
- 239000002826 coolant Substances 0.000 abstract description 14
- 229910052770 Uranium Inorganic materials 0.000 abstract description 9
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract description 9
- 238000006243 chemical reaction Methods 0.000 abstract description 3
- 239000012530 fluid Substances 0.000 abstract 1
- 239000000463 material Substances 0.000 description 15
- 239000002131 composite material Substances 0.000 description 7
- 230000004992 fission Effects 0.000 description 7
- 238000013461 design Methods 0.000 description 6
- 238000012958 reprocessing Methods 0.000 description 4
- 229910000831 Steel Inorganic materials 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 150000002222 fluorine compounds Chemical class 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 150000004820 halides Chemical class 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 229910004366 ThF4 Inorganic materials 0.000 description 2
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 229910002804 graphite Inorganic materials 0.000 description 2
- 239000010439 graphite Substances 0.000 description 2
- 229910052736 halogen Inorganic materials 0.000 description 2
- 150000002367 halogens Chemical class 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 229910001512 metal fluoride Inorganic materials 0.000 description 2
- 230000000717 retained effect Effects 0.000 description 2
- 229910052722 tritium Inorganic materials 0.000 description 2
- OYEHPCDNVJXUIW-FTXFMUIASA-N 239Pu Chemical compound [239Pu] OYEHPCDNVJXUIW-FTXFMUIASA-N 0.000 description 1
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 238000004873 anchoring Methods 0.000 description 1
- 238000003491 array Methods 0.000 description 1
- 229910052790 beryllium Inorganic materials 0.000 description 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 1
- 238000009395 breeding Methods 0.000 description 1
- 230000001488 breeding effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000003682 fluorination reaction Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- 229910001510 metal chloride Inorganic materials 0.000 description 1
- 229910001092 metal group alloy Inorganic materials 0.000 description 1
- 229910001507 metal halide Inorganic materials 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000004449 solid propellant Substances 0.000 description 1
- 230000003595 spectral effect Effects 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 229910000601 superalloy Inorganic materials 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- QKQVZMHSFHTREC-UHFFFAOYSA-K uranium trifluoride Chemical compound F[U](F)F QKQVZMHSFHTREC-UHFFFAOYSA-K 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/24—Fuel elements with fissile or breeder material in fluid form within a non-active casing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention describes a nuclear reactor having a core comprising an array of closed bottom hollow tubes which contain fissile isotopes in a molten form. The tubes are of asymmetric diameter, narrowing in a upper portion thereof so that critical mass cannot be achieved, thereby limiting the nuclear chain reaction to the lower portion of the core. The asymmetric diameter of the tubes also ensures there is sufficient space between the tubes in the upper sub-critical zone for an upwelling coolant fluid (the blanket) to escape laterally from the core without undue restriction. The liquid fuel preferably comprises fissile isotopes dissolved in a molten salt, but a liquid metal may also be used. The coolant is preferably also a molten salt, but may also contain a fertile isotope such as thorium or uranium.
Description
A SIMPLE LOW COST MOLTEN SALT THORIUM BREEDER NUCLEAR REACTOR
Background to the invention
Molten salt nuclear reactors are based on a critical mass of a fissile material dissolved in a molten salt. This is commonly referred to as fuel salt. They were pioneered at the Oak Ridge National Laboratory in the 1950's to 1970's but have never been successfully commercialised. They have several potential advantages over other reactor types which include the ability to breed fissile 233U from thorium, production of much lower levels of transuranic acdnide waste than uraniumlplutonium reactors, operation at high temperatures, avoidance of accumulation of volatile radioactive fission products in solid fuel rods and much higher burn up of fissile material than is possible in conventional reactors.
They have however never been commercialised. Two major factors have prevented this.
Many designs of molten salt reactors require attached reprocessing plants to remove fission products continually from the fuel salt. This is necessary to achieve effective breeding of new 233U from thorium since fission products act as neutron poisons, especially in moderated reactors based on a thermal neutron spectrum. It is also necessary to remove insoluble fission products which wou'd otherwise foul pumps and heat exchangers. Such reprocessing plant is complex. expensive and requires extensive development work.
Secondly. molten salts are highly corrosive. While nickel based superalloys are more resistant to such corrosion than standard steels, over long time penods corrosion would still occur.
Thus design and manufacture of essential components such as pumps and heat exchangers represents a major development challenge. In principle, new composite materials based on carbon and/or silicon carbide have the chemical resistance to withstand the molten salt but building complex structures such as pumps and efficient heat exchangers from such materials remains very challenging.
Recently, Mattieu and Lecarpentier (Nuclear Science and Engineering: 161, 78-89 (2009)) showed that a non moderated molten salt reactor could run for a decade or more without reprocessing. Their design still however invohed pumps and heat exchangers and could only be built after major research and development of materials for such components.
The object of this invention is to provide a molten salt nuclear reactor which can be built using currently available matenals and which requires no attached reprocessing plant. The design is extremely simple, consistent with factory rather than on site construction and should therefore have much lower capital cost than other molten sail reactor designs or conventional reactor designs. While the invention is particularly useful for reactors based on molten salts it is equally relevant to reactors based on other liquid nuclear fuels including molten metals.
Statement of the invention
The present invention involves the creation of a critical mass of fissile material by arranging multiple separate closed bottom hollow tubes, made from a material capable of containing hot molten fuel for long periods, containing a sufficient concentration of fissile isotopes in a liquid state to create a critical mass in an array of tubes contained within a tank of liquid coolant (the blanket). The tubes can be of circular cross section or any other suitable cross section including square and hexagonal shape but are of asymmetric diameter, narrowing in the upper portion of the tube so that the upper part of the tube array does not achieve critical mass, the nuclear chain reaction thus being limited to the lower portion of the tube array. The asymmetric diameter of the tubes ensures that there is sufficient space between the tubes in the upper subcritical zone for the upwelling heated blanket liquid to escape laterally from the core without the tubes unduly restricting the flow of the blanket liquid. Heat is removed from the coolant liquid in a heat exchanger. The coolant liquid is then returned to, or retained within, the tank.
Advantages The advantages of the inventive reactor over conventional reactors include the following.
Pumps and conventional heat exchangers are not required.
The thickness of blanket salt between the fuel tubes and tank wall can be increased to a thickness such that few neutrons reach the wall. This provides both supenor neutron economy and prevents the induction of radioactivity in the material of the tank wall and heat exchanger tubes.
The reactor has excellent intrinsic safety since both fuel salt and blanket are in physically and chemically stable forms and volatile fission products are continually removed to be stored safely.
All radioactive materials are held within a simple. robust tank which acts as an effective radiation screen.
All molten salts are held within the single tank making backup and start up heating systems very simple.
Description of the invention
The present invention involves the creation of a critical mass of fissile material by arranging multiple separate closed bottom hollow tubes, made from a material capable of containing hot molten fuel for long penods, containing a sufficient concentration of fissile isotopes in a liquid state to create a critical mass in an array of tubes contained within a tank of liquid coolant (the blanket). The tubes can be of circular cross section or any other suitable cross section including square and hexagonal shape but are of asymmetric diameter, narrowing in the upper portion of the tube so that the upper part of the tube array does not achieve critical mass, the nuclear chain reaction thus being limited to the thwer portion of the tube array. The asymmetric diameter of the tubes ensures that there is sufficient space between the tubes in the upper subcntical zone for the upwelling heated blanket liquid to escape laterally from the core without the tubes unduly restricting the flow of the blanket liquid. Heat is removed from the coolant liquid in a heat exchanger. The coolant liquid is then returned to, or retained within, the tank.
In a preferred embodiment, the liquid fuel is a molten salt containing salts of fissile isotopes and the coolant is also a similar or different molten salt.
In a further embodiment access is allowed through an apparatus at the top of each tube to allow additional materials to be added to the fuel salt and to allow evolved gasses from the fuel to be safely removed.
In a further embodiment, a temperature sensor is built into the apparatus at the top of the tube so that the temperature of the fuel salt can be monitored. This allows additional fissile material to be added to tubes so that each tube has an approximately equal temperature. It is a characteristic of this invention that the fuel salt in different tubes may differ in fissile isotope concentration, generally with tubes at the edge of the array having higher fissile isotope concentrations.
In a further embodiment the diameter of the tube expands in the uppermost part of the tube to provide a larger volume into which the heated fuel can expand and a more robust anchoring of the tube in the lid of the tank.
In a further embodiment, the blanket contains a fertile isotope such as thorium or uranium so that neutrons leaving the tube array are absorbed and generate new fissile isotopes.
In a further embodiment the heat exchanger comprises an array of tubes contained within the blanket tank, preferably at sufficient distance from the tube array to avoid exposure to high neutron flux so that only limited radioactivity is generated in the heat exchanger coolant. In this arrangement a convective flow of blanket liquid up through the fuel tube array and down through the heat exchanger tubes allows the use of pumps to be avoided.
In a further embodiment pumping systems are used to force the circulation of blanket liquid through the fuel tube array in order to increase the power output of the reactor beyond what can be achieved through natural convection.
In a further embodiment the heat exchanger coolant is water/steam which is passed directly to turbines to generate power.
in a further embodiment the heat exchanger coolant is a gas which is passed directly to a closed Brayton cycle turbine to generate electricity or passed to a steam generator to produce steam for use in steam turbines.
In a further embodiment the heat exchanger coolant is a molten metal or molten salt which is passed to a steam generator to generate steam to drive a turbine.
In a further embodiment the fuel and/or blanket salts are single or mixed metal chlorides or fluorides In a preferred embodiment the blanket salt is based on metal fluorides containing thorium tetrafluoride.
In a further embodiment the blanket salt does not contain lithium which generates tritium on exposure to neutrons.
In a further embodiment the blanket salt does not contain beryllium, which generates tritium on exposure to neutrons.
In a particularly preferred embodiment the blanket salt comprises sodium fluoride containing approximately 22 m&e% thorium tetrafluoride, In a preferred embodiment the tubes containing fuel salt are formed from carbon fibre/carbon composite material or from silicon carbide fibre/silicon carbide composite material or from mixed composites of carbon and sihcon carbide.
In a further embodiment there is a layer of molten metal that is compatible with the molten salt, preferably bismuth, lead or cadmium, that is mixed with thorium metal in the bottom of the tank. This metallic alloy or mixture reduces protactinium and uranium, which are created by neutron absorption by thorium in the blanket salt, to their metallic form which then dissolves in the molten metal. A mechanism is provided to periodically withdraw the molten metal from the tank and transfer it to a processing unit to recover the thorium and uranium.
In a further embodiment the layer of molten metal, preferably lead, bismuth or a mixture of the two is drawn from the bottom of the tank, passed through a steam generator or other heat exchanger and reintroduced at the top of the tank as a spray or many narrow Uquid c&umns which fall through the molten salt of the tank absorbing heat. This arrangement thus acts as the heat exchanger but without any need for physical separation of the blanket salt and heat exchanger coolant.
In a further embodiment the fuel salt is based on similar metal halide salts described as the basis for the blanket salt with the addition of fissile material. The fissile material can be any of, or a mixture of, the halides of 233uranium. 235uranium, 239plutonium or mixtures of uranium and transuranic elements recovered from used fuel from conventional nuclear reactors. It can also contain fertile isotopes including halides of 222thorium or 238uranium or mixtures thereof.
In a preferred embodiment the fuel contains halides in the form of fluorides.
In another embodiment the fuel contains a reductant that will be sacrificially oxidised by halogens generated during fission thereby protecting the tube wall from oxidation. Carbon is a preferred sacrificial reductant. Alternatively or additionally, uranium or thorium metal or lower valence fluorides can be used to maintain an equilibrium level of uranium trifluoride within the fuel which acts as the reductant to react with the halogens produced by fission.
In another embodiment the tank is lined with graphite or carbon composite, which has three functions. It protects the metal of the tank from corrosion by the molten salt. It insulates the tank from the high temperature molten salt. it reflects a proportion of any neutrons that reach the tank wall back into the blanket salt where they can be absorbed to breed further uranium.
EXAMPLE I
The primary containment vessel measures 7m by 4m by 3m high and is constructed of steel lined with graphite. It contains blanket salt comprising molten NaF containing 23 mole% ThF4 and a i0cm deep layer of molten bismuth at the bottom of the tank.
Fuel tubes are manufactured as a single piece from carbon fibre/carbon composite designed to have a high (>50 W/m.°C) thermal conductivity across the wall of the tube. The bottom I m has a diameter of 40mm, the upper I m has a diameter of 25mm and the top 300mm has a diameter of 40mm flaring to 45mm in the top 5cm. The tube wall is 3mm thick. The tubes are anchored in the steel lid of the containment vessel using a clamp fitting. 2000 tubes are arranged in a rectangular array Sm by Im at 50mm centers. The tubes are immersed in the molten salt leaving a 50mm space above the molten salt.
The fuel tubes are filled to the level of the top of the narrow region with molten fuel salt comprising NaF containing PuF3 and ThE. The concentration of PuF3 is calculated so as to achieve criticality in the particular tube. The concentration of ThF4 is adjusted so that the total heavy metal fluoride concentration is 23 m6Ie%. The top of the tube is dosed by the clamp fitting incorporating a tube connection to vent evolved gas.
Heat exchanger tubes are positioned in arrays occupying the 50cm of the blanket salt closest to the long wall of the tank. They are constructed from carbon fibre/carbon composite tubes which enter and leave the tank through the lid. Helium gas is passed through the tubes and passed to a steam generator which powers conventional steam turbines to produce electricity.
Additional fissile material is added through the clamp assembly as needed. The clamp assembly also contains a spectral temperature sensor to indicate when the fuel in the tube is falling below the desired temperature of 1000°C and therefore needs addition fissile material added.
The blanket salt temperature is maintained between 670°C and 870°C and circulates by convection up through the fuel tube array and down through the heat exchanger array.
Periodically, part of the bismuth layer is removed by inserting a pump assembly through a port in the lid of the containment vessel and transported to a fluorination plant where uranium is removed as the hexafluoride and the bismuth returned to the reactor. The uranium isolated, which is primarily 23U, is used either to top up the fuel tubes in the reactor or as fuel in new reactors.
Claims (2)
- CLAIMS1) A nuclear reactor where the core consists of an array of hollow tubes which are of wider diameter at their lower part than their upper part and which contain fissile isotopes in a molten form at a concentration such that the region of the tube array where the tube diameter is larger achieves critical mass while the region where the diameter is smaller does not achieve critical mass, the tube array being partially or totally immersed in a pool of a second liquid which by moving up through the tube array and laterally out through the upper part of the array where the tube diameters are smaller removes heat from the tube array into the pool of the second liquid from which it is subsequently removed by a heat exchanger mechanism.
- 2) The nuclear reactor of claim I where the movement of the second liquid through the array of tubes is by natural convection, thereby avoiding the need to pump the second liquid through the tube array 3) The nuclear reactor of claim 1 where the heat exchanger mechanism is immersed in the pool of the second molten salt thereby avoiding the need to pump the second liquid through the heat exchanger 4) The nuclear reactor of claim I where one or both of the liquids are metals 5) The nuclear reactor of claim I where one or both of the liquids are molten salts 6) The nuclear reactor of claim I where the fissile isotopes are dissolved in m&ten sodium fluoride 7) The nuclear reactor of claim I where the second liquid contains a fertile isotope which by absorption of a neutron is converted directly or indirectly into a fissile isotope.8) The nuclear reactor of claim 1 where the second liquid contains thorium 9) The nuclear reactor of claim I where the second liquid is a mixture of sodium fluoride and thorium tetrafluoride.10) The nuclear reactor of claim I where a layer of liquid metal, preferably lead, bismuth, cadmium or a mixture thereof is included at the bottom of the tank together with sufficient reductant, preferably sodium, lithium or thorium, to cause most fissile isotopes produced by neutron irradiation of the second liquid to be reduced to their metallic form and dissolved in the liquid metal.11) The nuclear reactor of claim I where a layer of liquid metal, preferably lead, bismuth, cadmium or a mixture thereof is included in the bottom of the tank and is pumped out of the tank, through an external heat exchanger or steam generator and then reintroduced at the top of the tank as a spray or large number of narrow streams of liquid so that it falls through the second liquid, directly cooling it.12) The nuclear reactor of claim I where the heat exchanger is an array of tubes immersed in the second liquid through which passes water and steam which directly power steam turbines external to the reactor 13) The nuclear reactor of claim 1 where the heat exchanger is an array of tubes immersed in the second liquid which are cooled by a molten salt, molten metal or a gas.14) The nuclear reactor of claim I where the aiay of hollow tubes and br the heat exchanger are manufactured from carbon, carbon fibre, silicon carbide, silicon carbide fibre or mixtures thereof.
Priority Applications (16)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1303279.2A GB2511113A (en) | 2013-02-25 | 2013-02-25 | A simple low cost molten salt thorium breeder nuclear reactor |
| GBGB1318470.0A GB201318470D0 (en) | 2013-02-25 | 2013-10-18 | A practical molten salt fission reactor |
| US14/768,658 US10043594B2 (en) | 2013-02-25 | 2014-02-19 | Practical molten salt fission reactor |
| EP14709360.3A EP2959487B1 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| RU2015136814A RU2644393C2 (en) | 2013-02-25 | 2014-02-19 | Molten-salt reactor |
| CN201480010226.8A CN105027224B (en) | 2013-02-25 | 2014-02-19 | A Practical Molten Salt Fission Reactor |
| PL14709360T PL2959487T3 (en) | 2013-02-25 | 2014-02-19 | Practical fission reactor with molten salts |
| GB1402908.6A GB2508537B (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| AU2014220481A AU2014220481B2 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| HK15112877.6A HK1212093A1 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| CA2902046A CA2902046C (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| KR1020157024426A KR102166205B1 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| ES14709360.3T ES2645140T3 (en) | 2013-02-25 | 2014-02-19 | Practical molten salt fission reactor |
| PCT/GB2014/050481 WO2014128457A1 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| JP2015558544A JP6596338B2 (en) | 2013-02-25 | 2014-02-19 | Fission reactor and method of operating the same |
| HUE14709360A HUE035509T2 (en) | 2013-02-25 | 2014-02-19 | Practical Molten Salt Fission Reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1303279.2A GB2511113A (en) | 2013-02-25 | 2013-02-25 | A simple low cost molten salt thorium breeder nuclear reactor |
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| Publication Number | Publication Date |
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| GB201303279D0 GB201303279D0 (en) | 2013-04-10 |
| GB2511113A true GB2511113A (en) | 2014-08-27 |
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| Application Number | Title | Priority Date | Filing Date |
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| GB1303279.2A Withdrawn GB2511113A (en) | 2013-02-25 | 2013-02-25 | A simple low cost molten salt thorium breeder nuclear reactor |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10141079B2 (en) | 2014-12-29 | 2018-11-27 | Terrapower, Llc | Targetry coupled separations |
| US10665356B2 (en) | 2015-09-30 | 2020-05-26 | Terrapower, Llc | Molten fuel nuclear reactor with neutron reflecting coolant |
| US10734122B2 (en) | 2015-09-30 | 2020-08-04 | Terrapower, Llc | Neutron reflector assembly for dynamic spectrum shifting |
| US10867710B2 (en) | 2015-09-30 | 2020-12-15 | Terrapower, Llc | Molten fuel nuclear reactor with neutron reflecting coolant |
| US11728052B2 (en) | 2020-08-17 | 2023-08-15 | Terra Power, Llc | Fast spectrum molten chloride test reactors |
| US11881320B2 (en) | 2019-12-23 | 2024-01-23 | Terrapower, Llc | Molten fuel reactors and orifice ring plates for molten fuel reactors |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1034870A (en) * | 1962-10-26 | 1966-07-06 | Atomic Energy Commission | Paste reactor |
-
2013
- 2013-02-25 GB GB1303279.2A patent/GB2511113A/en not_active Withdrawn
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1034870A (en) * | 1962-10-26 | 1966-07-06 | Atomic Energy Commission | Paste reactor |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10141079B2 (en) | 2014-12-29 | 2018-11-27 | Terrapower, Llc | Targetry coupled separations |
| US12002596B2 (en) | 2014-12-29 | 2024-06-04 | Terrapower, Llc | Targetry coupled separations |
| US12424343B2 (en) | 2014-12-29 | 2025-09-23 | Terrapower Isotopes, Llc | Separation of actinium from an irradiated source material including thorium |
| US10665356B2 (en) | 2015-09-30 | 2020-05-26 | Terrapower, Llc | Molten fuel nuclear reactor with neutron reflecting coolant |
| US10734122B2 (en) | 2015-09-30 | 2020-08-04 | Terrapower, Llc | Neutron reflector assembly for dynamic spectrum shifting |
| US10867710B2 (en) | 2015-09-30 | 2020-12-15 | Terrapower, Llc | Molten fuel nuclear reactor with neutron reflecting coolant |
| US11798694B2 (en) | 2015-09-30 | 2023-10-24 | Terrapower, Llc | Molten fuel nuclear reactor |
| US11881320B2 (en) | 2019-12-23 | 2024-01-23 | Terrapower, Llc | Molten fuel reactors and orifice ring plates for molten fuel reactors |
| US11728052B2 (en) | 2020-08-17 | 2023-08-15 | Terra Power, Llc | Fast spectrum molten chloride test reactors |
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| Publication number | Publication date |
|---|---|
| GB201303279D0 (en) | 2013-04-10 |
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