GB2516046A - A simple low cost molten salt nuclear reactor - Google Patents
A simple low cost molten salt nuclear reactor Download PDFInfo
- Publication number
- GB2516046A GB2516046A GB1312281.7A GB201312281A GB2516046A GB 2516046 A GB2516046 A GB 2516046A GB 201312281 A GB201312281 A GB 201312281A GB 2516046 A GB2516046 A GB 2516046A
- Authority
- GB
- United Kingdom
- Prior art keywords
- nuclear reactor
- liquid
- array
- tubes
- 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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Classifications
-
- 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
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with 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
- G21C1/022—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
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- 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
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—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
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 core is at least partially immersed in a tank of coolant (the blanket) which may also contain a heat exchange mechanism. In such an arrangement, a convective flow of blanket fluid moves up between the tubes in the array of the core and down through said heat exchange structure, thereby eliminating the need for pumps. 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 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 periods 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 aiay 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. 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 superior 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 sail 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 sails are hdd within the single tank making backup and star 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 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 suitaHe cross section including square and hexagonal shape. 1-leat is removed from the coolant Uquid 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 sail containing salts of fissile isotopes and the coolant is aho 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 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 the blanket contains a neutron absorber, hafnium being a preferred material, at sufficient concentration to absorb most neutrons before they reach the heat exchanger without preventing the array of fuel tubes from reaching cntical mass.
In a further embodiment, the flow of blanket salt within the tank is constrained by internal barriers within the tank so as to increase the velocity of the convective movement of the molten salt.
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 and increases the viscosity of the molten salt.
In a particularly preferred embodiment the blanket salt comprises sodium fluoride or a mixture of sodium and potassium fluoride containing approximately 22 mole% thorium tetrafluoride.
In a preferred embodiment the tubes containing fuel salt are formed from graphite or from carbon fibre/carbon composite material or from silicon carbide fibre/silicon carbide composite material or from mixed composites of carbon and silicon 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 unmium, 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 liquid columns 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 223uranium, 225uranium. r9plutonium or mixtures of uranium and transuranic elements recovered from used fuel from conventional nuclear reactors. It can also contain fertile isotopes including halides of 22thorium or 28uranium 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 sail. 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.
EXAMPLE I Breeding version of the reactor The primary containment vessel is cylindrical with a diameter of 4m and a depth of 3m and is constructed of steel lined with graphite. It contains blanket salt comprising molten NaP containing 23 mole% ThF4 and a 10cm deep layer of molten bismuth at the bottom of the tank.
Fuel tubes are manufactured as single pieces from nuclear grade graphite having a high (>50 W/rn.°C) thermal conductivity across the wall of the tube. The tube wall is 3mm thick and the tubes have a diameter of 4cm and a length of 3m. The tubes are anchored in the lid of the containment vessel using a clamp fitting. Approximately 2000 tubes are arranged in a circular array of 2m diameter in a hexagonal alTangement with a minimum gap between fuel tubes of 1cm. The tubes are immersed in the molten salt leaving a 50mm space above the molten salt which is filled with helium gas.
The fud tubes are filled to a depth of 2m with molten fuel salt comprising NaP containing PuF and ThF4 The concentration of PuF in each tube is calculated so that each tube reaches a similar temperature when the reactor is operational. The concentration of ThF4 is adjusted so that the total heavy metal fluoride concentration is 23 mole%. The top of the tube is closed 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 external wall of the tank. They are constructed from molten salt resistant nickel alloy and contain water/steam pumped through the tubes at a rate such that the exit temperature of the steam is approxirnatdy 300°C.
Additional fissile material is added through the clamp assembly as needed to maintain the temperature of the fuel salt as fissile material is consumed and fission products accumulate.
The clamp assembly also contains a spectral temperature sensor to indicate when the fuel in the tube is falling below the desired temperature of 950°C and therefore needs addition of fresh fissile material.
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 233U, is used either to top up the fuel tubes in the reactor or as fuel in new reactors.
EXAMPLE 2 Non breeding version of the reactor The primary containment vessel is cylindrical with a diameter of 4m and a depth of 3m and and is constructed of steel lined with graphite. It contains a blanket salt comprising a eutectic mixture of NaF, KF and PbF2.
Fuel tubes are manufactured as single pieces from nuclear grade graphite having a high (>50 W/m.°C) thermal conductivity across the wall of the tube. The tube wall is 3mm thick and the tubes have a diameter of 4cm and a length of 3m. The tubes are anchored in the lid of the containment vessel using a clamp fitting. Approximately 2000 tubes are arranged in a circular array of 2m diameter in a hexagonal arrangement with a minimum gap between fud tubes of 1cm. The tubes are immersed in the m&ten sail leaving a 50mm space above the moilen salt which is filled with helium gas.
The fuel tubes are filled to a depth of 2m with molten fuel salt comprising NaF/KF containing mixed actinides (Np, Pu, Am, Cm) from reprocessed nuclear fuel and ThF4 The concentration of actinides in each tube is calculated so that each tube reaches a similar temperature when the reactor is operational. The concentration of ThE4 is adjusted so that the total heavy metal fluoride concentration is 23 mole%. The top of the tube is closed 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 external wall of the tank. They are constructed from molten salt resistant nickel alloy and contain water/steam pumped through the tubes at a rate such that the exit temperature of the steam is approximately 300°C.
Additional fissile material is added through the clamp assembly as needed to maintain the temperature of the fuel salt as fissile material is consumed and fission products accumulate.
The clamp assembly also contains a spectral temperature sensor to indicate when the fuel in the tube is falling below the desired temperature of 900°C and therefore needs addition of fresh fissile matenal.
The blanket salt temperature is maintained between 570°C and 770°C and circulates by convection up through the fuel tube array and down through the heat exchanger array.
Claims (2)
- CLAIMS1) A nuclear reactor where the core consists of an array of closed bottom hollow tubes which contain fissile isotopes in a molten form, 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 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 1 where the 3) 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 4) The nuclear reactor of claim I where the array of tubes is approximately circular.5) The nuclear reactor of claim I where the spacing of the array of tubes is arranged to optirnise lateral flow of the second liquid out of the array 6) The nuclear reactor of claim I 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 7) The nuclear reactor of claim I where one or both of the liquids are metals 8) The nuclear reactor of claim I where one or both of the liquids are molten salts 9) The nuclear reactor of claim I where the fissile isotopes are dissolved in molten sodium fluoride 10) The nuclear reactor of claim I where the fissile isotopes are dissolved in a mixture of sodium and potassium fluondes 11) The nuclear reactor of claim I where the second liquid contains a sufficient amount of a neuon absorbing isotope that the heat exchanger is substantially protected from the neutron flux originating in the fuel tube array 12) 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.13) The nuclear reactor of claim 1 where the second liquid contains thorium 14) The nuclear reactor of claim 1 where the second liquid is a mixture of sodium fluoride and thorium tetrafluoride.15) The nuclear reactor of claim I where the second liquid is a mixture of sodium fluoride, potassium fluoride and thorium tetrafluoride 16) 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.17) The nuclear reactor of claim 1 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.18) The nuclear reactor of claim I where the heat exchanger is an array of tubes immersed in the second liquid through which pass water and steam which power steam turbines external to the reactor 19) 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.20) The nuclear reactor of claim I where the array 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 |
|---|---|---|---|
| GB1312281.7A GB2516046A (en) | 2013-07-09 | 2013-07-09 | A simple low cost molten salt nuclear reactor |
| GBGB1318470.0A GB201318470D0 (en) | 2013-02-25 | 2013-10-18 | A practical molten salt fission reactor |
| AU2014220481A AU2014220481B2 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| CN201480010226.8A CN105027224B (en) | 2013-02-25 | 2014-02-19 | A kind of practical fused salt fission reactor |
| PL14709360T PL2959487T3 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| EP14709360.3A EP2959487B1 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| PCT/GB2014/050481 WO2014128457A1 (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| GB1402908.6A GB2508537B (en) | 2013-02-25 | 2014-02-19 | A practical molten salt fission reactor |
| US14/768,658 US10043594B2 (en) | 2013-02-25 | 2014-02-19 | Practical molten salt fission reactor |
| KR1020157024426A KR102166205B1 (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 |
| HUE14709360A HUE035509T2 (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 |
| JP2015558544A JP6596338B2 (en) | 2013-02-25 | 2014-02-19 | Fission reactor and method of operating the same |
| ES14709360.3T ES2645140T3 (en) | 2013-02-25 | 2014-02-19 | Practical molten salt fission reactor |
| HK15112877.6A HK1212093A1 (en) | 2013-02-25 | 2015-12-31 | A practical molten salt fission reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1312281.7A GB2516046A (en) | 2013-07-09 | 2013-07-09 | A simple low cost molten salt nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB201312281D0 GB201312281D0 (en) | 2013-08-21 |
| GB2516046A true GB2516046A (en) | 2015-01-14 |
Family
ID=49033536
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1312281.7A Withdrawn GB2516046A (en) | 2013-02-25 | 2013-07-09 | A simple low cost molten salt nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB2516046A (en) |
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 |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB922041A (en) * | 1960-04-14 | 1963-03-27 | Harry Norman Schludi | Improvements in or relating to the operation of nuclear reactors |
| US3085966A (en) * | 1960-11-08 | 1963-04-16 | North American Aviation Inc | Liquid homogeneous fuel element and reactor therefor |
| US3251745A (en) * | 1961-12-11 | 1966-05-17 | Dow Chemical Co | Nuclear reactor and integrated fuelblanket system therefor |
| GB1034870A (en) * | 1962-10-26 | 1966-07-06 | Atomic Energy Commission | Paste reactor |
| GB1192507A (en) * | 1967-11-15 | 1970-05-20 | Atomic Energy Commission | Method of Operating a Nuclear Reactor |
-
2013
- 2013-07-09 GB GB1312281.7A patent/GB2516046A/en not_active Withdrawn
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB922041A (en) * | 1960-04-14 | 1963-03-27 | Harry Norman Schludi | Improvements in or relating to the operation of nuclear reactors |
| US3085966A (en) * | 1960-11-08 | 1963-04-16 | North American Aviation Inc | Liquid homogeneous fuel element and reactor therefor |
| US3251745A (en) * | 1961-12-11 | 1966-05-17 | Dow Chemical Co | Nuclear reactor and integrated fuelblanket system therefor |
| GB1034870A (en) * | 1962-10-26 | 1966-07-06 | Atomic Energy Commission | Paste reactor |
| GB1192507A (en) * | 1967-11-15 | 1970-05-20 | Atomic Energy Commission | Method of Operating a Nuclear Reactor |
Cited By (7)
| 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 |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| GB201312281D0 (en) | 2013-08-21 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |