WO1999045545A1 - Nuclear powered steam expansion engine and a nuclear powered generator with method of operation - Google Patents
Nuclear powered steam expansion engine and a nuclear powered generator with method of operation Download PDFInfo
- Publication number
- WO1999045545A1 WO1999045545A1 PCT/US1999/005448 US9905448W WO9945545A1 WO 1999045545 A1 WO1999045545 A1 WO 1999045545A1 US 9905448 W US9905448 W US 9905448W WO 9945545 A1 WO9945545 A1 WO 9945545A1
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- WO
- WIPO (PCT)
- Prior art keywords
- fuel assembly
- nuclear fuel
- nuclear
- piston
- power generator
- Prior art date
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/02—Reactor and engine structurally combined, e.g. portable
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/30—Control of nuclear reaction by displacement of the reactor fuel or fuel elements
-
- 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
- Y02E20/00—Combustion technologies with mitigation potential
- Y02E20/16—Combined cycle power plant [CCPP], or combined cycle gas turbine [CCGT]
-
- 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
-
- 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
Definitions
- the present invention relates to a nuclear power generator capable of using fresh or spent nuclear fuel to generate power.
- the generator provides an apparatus for moving an assembly of fresh nuclear fuel into and out of proximity to a second nuclear fuel assembly so that the moving assembly experiences consecutive subcritical and supercritical states. The result is both a cyclical release of power by the fresh fuel assemblies, and the periodic availability of a source of delayed neutrons, which can be used to elevate an assembly of spent nuclear fuel into a supercritical state for additional power generation.
- the expansion device i.e. turbine
- the steam admission valve system controlling the flow of the working fluid into the expander.
- the expansion devices can be classified into two categories: low-speed systems such as positive-displacement devices, and high-speed systems such as turbines.
- Conventional turbines are usually not suitable for Rankine power cycle application owing to their low efficiencies when operating with the Rankine constraint.
- An objective of this invention is to provide a special expander connected through a valve system to a conventional turbine.
- the special expander is characterized by the integration of the boiler into the expansion chamber of a conventional piston-cylinder assembly. In this manner, the fluid friction losses through the control valve system and the efficiency loss associated with the heat addition process in the conventional boiler are reduced.
- One goal of this invention is to provide a heat-work conversion engine with efficiency greater than that of conventional systems.
- NPSEE nuclear powered steam expansion engine
- An object of the present invention is to provide an apparatus, and a method, of ultimately producing electric power with a high efficiency, thereby overcoming the low efficiency characteristics of conventional power plants. It is a further object of the invention to provide an apparatus for generating nuclear power using spent nuclear fuel by transferring an assembly made of fresh fuel between a nuclear reactor containing fresh fuel, where it achieves supercriticality and a reactor containing spent fuel which is thereby raised to a supercritical state.
- An apparatus are presented which use the time-variant transition of the moving fuel assembly from subcriticality to supercriticality in the generation of power. These include externally driven hydraulic and mechanical devices that impart periodic motion to the moving fuel assembly. Also included is a nuclear powered steam expansion engine that moves the fuel assembly using internally generated mechanical energy. This mechanical energy is converted internally from the heat of the nuclear reaction itself.
- the nuclear powered steam expansion engine includes high pressure liquid water forced inside specially designed heat cavities hydraulically connected and sealed to a piston cylinder assembly. Considering only one cavity, the high pressure liquid water enters the cavity through a high-pressure injector(s) that opens in synchronism which the position of the piston and as a function of the relative stroke.
- the piston is found a few crankshaft degrees ("crank") below its top dead center (TDC) position, while the exhaust valve is kept closed.
- TDC top dead center
- the piston is forced toward its bottom dead center (BDC) position, thereby producing the power stroke.
- BDC bottom dead center
- the exhaust valve opens and vents steam to a conventional turbine system through a steam expansion valve.
- the piston moves upward, forcing steam through the heat cavities in which heat is transferred to the steam one more time.
- superheated steam is available for further expansion in the turbine(s) producing additional work.
- the power cycle starts again when the exhaust valve closes and the piston is re-positioned a few degrees below the TDC position re-activating, through electromechanical links, the high-pressure injectors. Overall, the cycle is completed in two strokes, the power stroke and the exhaust stroke corresponding to exactly one 360 degree rotation of the crankshaft.
- the temperature on the surfaces of the heat cavities changes as a function of variable fission rate, which is mainly affected by the motion of the piston.
- the piston can be considered as a source of neutrons (mainly delayed) which are emitted even when it is found in its BDC position. Therefore, by utilizing this characteristic for graphite moderated reactor, located under the water moderated reactor, it is possible to recycle spent fuel since it still contains a considerable fraction of natural uranium.
- Fig. 1 is a sectional view of an embodiment of the nuclear powered steam expansion engine in accordance with the present invention.
- Fig. 2 is a sectional view of a simplified representation of the high pressure fluid injector(s), taken along line l-l and V-V of Fig. 1.
- Fig. 3 is a sectional view of a simplified representation of the cavity containing nuclear fuel assemblies, taken along lines Ill-Ill and IV-IV of Fig. 1.
- Fig. 4 is a sectional view of the transfer cavities placed in the piston with their relative inlet ports exposed to the fluid injectors.
- Fig. 5 is a simplified sectional view of the core of the NPSEE in which sets of control rods are utilized in the same manner as for conventional pressurized water reactors (PWRs).
- PWRs pressurized water reactors
- Fig. 6A is a fragmentary perspective view of the piston, piston-supported fuel assembly, and cylinder with the piston near top dead center.
- Fig. 6B is a vertical section through the center of the piston and piston-supported fuel assembly of Fig. 6.
- Fig. 6C is a fragmentary section of the injectors, cylinder, and piston-supported fuel assembly taken along line 6C-6C of Fig. 6B.
- Fig. 7 is the model of fissile material rich piston that upon insertion inside a fissile material rich cylinder that overcomes the critical condition to produce heat, steam and ultimately work.
- Fig. 8 is the analogue of the NPSEE configured for the recycling of fuel to be positioned in the graphite-moderated reactor located under the water moderated reactor.
- Fig. 9 is a schematic of the thermodynamic processes occurring in the NPSEE to form the highly efficient NPSEE thermodynamic cycle.
- Fig. 10 is a T-S diagram of the NPSEE thermodynamic cycle in which two reference crankshaft speeds are considered.
- Fig. 11 is a fragmentary perspective view of the nuclear power generator having both fresh fuel and spent fuel reactors according to the invention.
- Fig. 12 is schematic view showing a hydraulically actuated apparatus for moving fuel assemblies between a reactor containing fresh nuclear fuel and a reactor containing spent or natural nuclear fuel.
- Fig. 13 is a schematic view showing a mechanically actuated apparatus for moving fuel assemblies between a reactor containing fresh nuclear fuel and a reactor containing spent or natural nuclear fuel.
- the steam expansion engine apparatus has a plurality of units: 1 , 3, 14, 7, 18 ,20 and 22, which are connected in series through connecting pipes as to form the closed loop of a thermodynamic power cycle.
- the steam expansion apparatus of the present invention has a high-pressure pump in which de-mineralized and de-ionized water is pressurized into a discharge tube to a pressure level such that a series of spring loaded valves (injectors) open, spraying water droplets into high temperature cavities in which water flashes to steam.
- the rapid expansion of steam causes a pressure increase inside the cylinder-piston assembly.
- Water is the working fluid considered in this design but any other fluid having the proper thermodynamic, physical and neutron moderation characteristics can be utilized.
- unit 1 represents a high-pressure pump that is characterized by one inlet 29 and one exit 2.
- the fluid is tin the liquid state at the post-reactor 14 conditions.
- the fluid is at the high-pressure liquid state with a temperature not much different than the inlet temperature.
- the thermodynamic state of the fluid at the inlet 29 of pump 1 is characterized by a pressure of about 80 bars and a temperature of approximately 230 C. The saturation temperature at this pressure is about 295 C, therefore, the fluid state is found in the sub-cooled liquid region.
- the pressure of reactor 14 is kept at the constant value of 80 bars by utilizing the pressurizer 38 that operates in the same manner as a conventional PWR pressurizer.
- Pump 1 has the purpose of changing the pressure of the liquid water at the exit 29 of the reactor 14 from the reactor pressure, about 80 bars, to a pressure of about 90 bars (1323 psi), which is the minimum, pressure value necessary to open the injectors 3,2-1 a and 24b.
- Compressor 1 is mechanically linked, through the gear system 10, to the crankshaft 26 so that the rotation of the compressor impeller blades 27 is synchronized with the position of the crankshaft 26. In this manner the fluid is compressed in a pulse-like fashion, as in the case for Diesel injectors pumps.
- the fluid is cyclically pressurized into the discharging tube 2, which is hydraulically connected to the discharging tubes 25 and 25b and ultimately connected to the body of a series of high pressure injectors 3, 24a and 24b.
- the pressure at the discharging tube 2 is equalized for all of the high pressure injectors through the hydraulic connection 25a and 25b but, if necessary, by changing the injectors' spring constant, it is possible to delay the opening of one series of injectors with respect to another series of injectors so as to control the rate of expansion of the fluid in different locations of the expansion chamber 36.
- the water injectors 3, 24a and 24b are spring-loaded valves (these representations are not to scale).
- a calibrated spring 4 mechanically connected to an injection nozzle valve 5.
- the injection nozzle of valve 5 opens.
- the injection nozzle valve 5 is contained in each series of injectors 3, 24a and 24b. As soon as valve 5 opens, the pressure in the discharging tube 2, 25a and 25b drops rapidly, causing valve 5 to close again.
- thermodynamic state changes very rapidly, going from a state of pressurized sub-cooled liquid to a two-phase liquid-vapor state and finally to a superheated state. This thermodynamic change induces a significant increase of the pressure inside the piston 12 and cylinder assembly 33.
- Nuclear reactor criticality indicated with the symbol "k”, is the conventional term utilized to define the ratio of neutrons generated at a given time to the number of neutrons generated at a pervious time. In other words, it provides a measure that defines the rate of fission reactions.
- the reactor is in the super-critical configuration when, in its whole, the nuclear fuel assemblies 13, 14 and 7 form a generally contiguous mass.
- the reactor formed by the nuclear fuel assemblies 13, 14 and 7 is cyclically found in a slightly super-critical condition subsequent to a sub-critical condition depending on the position of piston 12 and the control rods 31.
- the super-critical condition (k> 1) corresponds to the TDC position of piston 12, while the sub-critical condition is at its maximum, in absolute value, when piston 12 is found in the BDC position.
- the control rods 31 represented in Fig. 5 are utilized in the same manner as conventional control rods are utilized in PWRs. Therefore, as represented in Fig. 5, at the reactor start-up the control rods 31 will be found inserted into the guiding tubes 16 and withdrawn gradually during normal operation and/or depending on fuel burn-up.
- the negative reactivity insertion can be designed such that it is much higher, in absolute value, than the positive reactivity insertion that occurs when the piston 12 is found inside the reactor 14 and corresponding to the piston TDC position.
- the fluid injection phase starts when the inlet ports 32 in Fig. 1 are exposed to the outlet of the fluid injectors 33.
- the camshaft 28 synchronized with the position of the piston 12 through the mechanical link 11 , sets the rotation of blades 27 of compressor 1 for the injection phase.
- the exhaust valve 8 is forced closed due to the action of the spring 130, as shown on Fig. 4, which is relatively uncompressed due to the position of the mechanical link 9.
- the piston 12 is still moving upward and before it has reached the TDC position, all of the injectors 3, 24a and 24b have completed their fluid injection phase through the discharging tubes 2, 25a and 25b.
- the initiation and duration of the injection phase is a function of the position of crankshaft 28.
- the piston 12 When the piston 12 is found in the TDC position, it inserts a positive reactivity resulting in a very rapid increase in the temperature of the heat cavity surfaces. The condition is timed and synchronized with the initiation and termination of the fluid injection phase.
- the NPSEE cycle starts again as soon as the piston 12 is found a few crankshaft degrees before the TDC position.
- the exhaust valve 8 closes and the fluid injection phase starts again.
- the piston 12 inserts a new wave of prompt neutrons superimposed on a reactivity condition dominated by the delayed neutrons generated in the previous stroke.
- nuclear feedback such as moderator coefficient, Doppler effect and others are not present, the reactivity would increase in a sinusoidal fashion superimposed on an exponential reactivity insertion.
- the exponential power rising effect can be stabilized to a steady-state average power.
- the reactivity will be oscillating as a sinusoidal function of time (directly proportional to the non-harmonic motion of the piston) superimposed on an average reactivity value.
- the amplitude of the sinusoidal-like reactivity insertion is determined by the position of the control rods 31 and the speed at which the piston cyclically inserts the fissile material 13 inside the reactor 14 and 7.
- the wave form of the time dependant reactivity is determined by the non-harmonic motion of the piston 12 and its approach to the internal part of the reactor 145.
- compressor 22 represents a pump for the cooling of the nuclear fuel assemblies placed in the reactor 14 and 39, in Fig. 3.
- the coolant in this section of the reactor is the same fluid utilized for the expansion process, but, to improve safety, it is possible to separate the two parts of the overall reactor constituted by sections 7, 13 and 14 into two independent hydraulic circuits.
- the methodology and the designed safety features of the steam expansion engine can be the same as those applied for conventional nuclear reactors. Whit reference to Fig. 1 , it is assumed that the reactor 14 is built with the same concepts utilized in the design of conventional PWR/BWR reactors.
- the primary vessel 35 and the secondary vessel 37 surrounding the primary vessel.
- the primary vessel structure surrounds the head of the fluid expansion chamber 36, which is part of the cylinder 35, and surrounds the fuel assemblies 7 so as to form the gap 6 in which the fluid is forced to an intimate contact with the hot surfaces of the fuel assemblies.
- the internal structure of both primary and secondary vessels consists of fuel assemblies, instrumentation, thermal shielding and so on a suited for conventional nuclear reactors.
- the reactivity can be controlled by moving the control rods 31 (Fig. 5), by changing the concentration of neutron absorbers diluted in the working fluid which is the moderator itself, and by changing the speed at which the piston 12 approaches and enters the reactor 14.
- An additional inherent safety feature offered by the design is related to the time dependent geometry of the steam expansion engine. Since the reactor is formed by moving parts, it implies a reactor sub-critical condition whenever the piston 12 is found in the BDC position. In this case, the subsequent negative reactivity inserted in the neutronic system can be such that the overall reactor shuts down automatically. Therefore, by locking piston 12 at it bottom dead center position, the reactor remains in a shut-sown condition even if the rods 31 are completely withdrawn. In other words, the design guarantees the shut-down condition even in the absence of control rods 31 and the chemical neutron absorbers diluted in the working fluid.
- the overall reactor can be seen as composed by a fast neutron region, located in the areas adjacent to the heat cavities, such as the areas surrounding the gap 6, the fuel assemblies 13 and 7, and a thermal-neutron region characterized by the fuel assemblies located in the reactor 14.
- the working fluid utilized for the expansion process, can also constitute the media needed for the neutron moderation, but this is not a limitation.
- the primary vessel 35 can be hydraulically independent of the secondary vessel 37, and the fluids utilized in the two hydraulic systems can be different in nature.
- the working fluid is also considered to be the moderator owing to its neutron scattering characteristics, it becomes clear that the nuclear fuel contained in the heat cavities 23 (Fig. 3) and 34 (Fig. 6) is exposed to fast neutrons. The neutron scattering in these regions occurs with steam whose low density decreases the probability for neutron-hydrogen interaction.
- the neutron mean free path in these regions of the reactor has an order of magnitude comparable to the gap distance 6, therefore neutrons in these areas of the reactor cannot be slowed down to energies in the thermal range.
- the rest of the reactor, and in particular the nuclear fuel contained in the fuel assemblies 14, can be treated with the methodology applied for conventional thermal reactors.
- the overall NPSEE reactor can be composed of three parts: the pistons, the pressurized vessel surrounding the pistons, and a graphite moderated thermal reactor located above the crankshaft 39. Therefore, the pistons 13 can been seen as a source of neutrons (mostly delayed) which can cyclically inserted insider the graphite moderated reactor 99.
- the fuel utilized in this section of the reactor is characterized by natural uranium contained in the spent or un- enriched nuclear fuel rods of assemblies 40. In other words, the fuel utilized in the water moderated reactor 14 can be recycled in the graphite moderated reactor 39.
- the radius of the graphite moderated reactor 39 is in the range of 3 to 4 meters and the number of pistons utilized can be varied.
- each piston 13 is cyclically inserted inside the water- moderated reactor 14 (Fig. 8) while it exits the graphite-moderated reactor 39. During the following stroke, each piston exits the water-moderated reactor 14 and enters the graphite-moderated reactor 39. This situation is repeated every 180 crank 0 .
- the fission reactions occurring in the fuel assemblies contained in the pistons 13 produce fission fragments which will decay by emitting delayed neutrons. Since the pistons 13 spend 50% of the time outside the water-moderated reactor 14 (or inside the graphite moderated reactor 39) a significant quantity of neutrons is emitted when the piston is moving toward the BDC position. Normally, depending on geometry, the critical condition for large natural uranium reactors (non-enriched or spent fuel) is fairly close to unity, making such reactors impractical. However, if an additional and significant source of neutrons is cyclically introduced in the neutron balance of such reactors, the overall criticality can be greater than unity, thereby leading these reactors to the super-critical condition again.
- Fig. 9 and fig. 10 the NPSEE thermodynamic cycle is represented.
- Processed 1-2,2-3 and 3-4 correspond to the compression/expansion processes occurring in the piston/cylinder(s) expander when valve(s) 8, in fig. 1 and/or Fig. 8, is kept close.
- Considering only one piston as is shown in Fig. 1 as the power stroke terminates the mechanical links presented by systems 9 and 10 open the exhaust valve 8 venting the exhaust steam to the turbine 18.
- FIG. 9 This process 4-5 in Fig. 9 an Fig. 10 characterized further heat addition during the exhaust stroke.
- Processes 5-6, 6 7 and 7-8 in Fig. 9 represent the steam expansion in the turbin 18, the heat recovery in the heat exchanger 21 and the condensation process in the condenser 20 as is shown Fig. 1 and 5.
- the compression process 8-0 in Fig. 9 and Fig. 10 is achieved by the high pressure pump 22 represented in Fig. 1 and Fig. 5.
- process 0-01 is a heat addition process occurring at the heat exchanger 21 shown in Fig. 1 and Fig. 5.
- process 01-02 represents the heat addition process occurring in the reactor 14 prior to the pressurization in pump 1 as is shown in fig. 1.
- NPSEE is configured for spent fuel recycling as is shown in Fig. 8, process
- 01-02 represents the heat addition of the pressurized water (pressurized through pump 22) which cools down the graphite moderated reactor 39 and the water moderated reactor 14 before exiting at the exit 29 as is sown in Fig. 1 and
- FIG. 8 Process 03-1 in Fig. 9 and Fig. 10 represents the heat addition processes occurring in the heat cavities 23 (Fig. 3), and the heat cavities 7 and
- thermodynamic cycle of the NPSEE is a sequence of twelve processes in which the expansion of steam occurs alternately in two expansion systems, the piston-cylinder assembly 13-35, and the turbine(s) 18.
- the efficiency of this cycle is strongly dependent on the amount of water injected through the injectors 3, 24b and
- Fig. 11 illustrates a more general embodiment of the reactor, described above, which can generate useful energy with spent or un-enriched nuclear fuel.
- the nuclear power generator shown includes a first nuclear reactor 70 that is referred to as the giver reactor.
- This giver reactor 70 has giver nuclear fuel assemblies 72 that include fresh or enriched nuclear fuel.
- the generator also includes a second nuclear reactor 74 that also has fuel assemblies 76.
- the second nuclear reactor 74 is referred to as the taker reactor, and the taker fuel assemblies it contains include spent or un-enriched nuclear fuel.
- the taker nuclear fuel assembly 76 is disposed adjacent to the giver fuel assembly 72.
- the giver reactor may be a water moderated reactor, a heavy-water moderated reactor, a graphite moderated reactor, or a reactor moderated by a combination of the above.
- the taker reactor is generally a graphite moderated reactor, although graphite equivalent materials or combinations of materials may be used.
- a plurality of third nuclear fuel assemblies 78 which also include fresh fuel and are thus net givers of neutrons, are supported for movement between a first position 80 near the giver fuel assembly and a second position 82 near the taker fuel assembly.
- These third nuclear fuel assemblies 78 are first disposed adjacent to the first nuclear fuel assembly 72 at position 80 and spaced from said second nuclear fuel assembly 76 at position 82.
- the first nuclear fuel assembly 72, and the third nuclear fuel assembly 78 are supercritical.
- the second fuel assembly 76 is subcritical.
- the third nuclear fuel assembles 78 are disposed adjacent to the second nuclear fuel assembly 76 at position 82 and spaced from the first nuclear fuel assembly 72.
- the first nuclear fuel assembly 72 is subcritical and the second nuclear fuel assembly 76 is, at least for a time, supercritical.
- the motion of the assemblies 78 may be synchronized to insure that the position of each is out of time and position phase with one or more other assemblies, so as to minimize time variation in the power or heat released by the reactors 70,74.
- each rod 98 since the movement of each rod 98 is independent it is possible to cycle their insertion inside reactor 70 or 74 as desired so as to generate a smooth transition from sub-critical to super-critical throughout the two reactors.
- the mechanism that transfers assemblies 78 from one reactor to another is independent and does not require steam as a driving force as it was necessary in the reactor configuration of Fig. 1 and Fig. 9.
- the means for moving the third nuclear fuel assemblies 78 between the first position 80 near the giver reactor 70 and the second position 82 near the taker reactor 72 need not be a steam engine. Any appropriate means, such as mechanical, hydraulic, pneumatic, electromotive, etc. would do.
- An exemplary embodiment utilizing hydraulic actuation is illustrated in Fig. 12. This embodiment shows an arrangement including a hydraulic power source 90, valve means 92 which may include a controller 94 to periodically operate the valve means, connecting piping 96, a pair of moving fuel assemblies 78, each within a cylinder 100, and a reservoir 102 of hydraulic fluid 104 capable of transferring energy from the hydraulic power source 90 to the moving fuel assemblies 98.
- fluid 104 is forced through the piping 96 and valve assembly 92 by the power source 90 (generally a pump) to apply pressure either against an end 106 or end 108 of fuel assemblies 78.
- the fluid 104 may or may not be able to move past the fuel assembly depending on the specific desired relationship between the wall 110 of the cylinder 100.
- the hydraulic fluid 104 may serve in some measure to cool the nuclear fuel assemblies 78.
- a change in valve setting reverses the flow of hydraulic fluid 104, with a consequent reversal in the direction of the motion of the fuel assemblies 78.
- Fig. 13 illustrates another embodiment providing similar operation but through mechanical means.
- a cable or other flexible member 120 is attached between the first ends 122 of a pair of fuel assemblies 78, and a second flexible member 124 is attached between the corresponding second ends 126 of the same fuel assemblies.
- the fuel assemblies 78 reside in tubes 128.
- a driving means 126 for example a motor driven pulley, capstan, or spool, engages at least one of the flexible members 120 or 124, and imparts motion to the flexible member, which in turn draws the fuel assemblies 78 between respective first and second positions in reciprocating fashion.
- Various idler pulleys 132 may be used to ease the passage of the flexible members 120 and 124 through the apparatus.
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Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP99917304A EP1074024A4 (en) | 1998-03-05 | 1999-03-05 | Nuclear powered steam expansion engine and a nuclear powered generator with method of operation |
AU35456/99A AU3545699A (en) | 1998-03-05 | 1999-03-05 | Nuclear powered steam expansion engine and a nuclear powered generator with method of operation |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
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US7691798P | 1998-03-05 | 1998-03-05 | |
US60/076,917 | 1998-03-05 |
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WO1999045545A1 true WO1999045545A1 (en) | 1999-09-10 |
WO1999045545A8 WO1999045545A8 (en) | 2000-03-02 |
WO1999045545A9 WO1999045545A9 (en) | 2000-04-27 |
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PCT/US1999/005448 WO1999045545A1 (en) | 1998-03-05 | 1999-03-05 | Nuclear powered steam expansion engine and a nuclear powered generator with method of operation |
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AU (1) | AU3545699A (en) |
WO (1) | WO1999045545A1 (en) |
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EP3308380A4 (en) * | 2015-04-09 | 2019-06-19 | Claudio Filippone | Transportable sub-critical modules for power generation and related methods |
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US9947423B2 (en) | 2013-08-23 | 2018-04-17 | Global Energy Research Associates, LLC | Nanofuel internal engine |
US11450442B2 (en) | 2013-08-23 | 2022-09-20 | Global Energy Research Associates, LLC | Internal-external hybrid microreactor in a compact configuration |
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Citations (20)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2790761A (en) * | 1952-05-16 | 1957-04-30 | Leo A Ohlinger | Neutronic reactor |
US2812304A (en) * | 1946-01-09 | 1957-11-05 | John A Wheeler | Means for cooling reactors |
US2875143A (en) * | 1956-07-16 | 1959-02-24 | Darol K Froman | Push-pull power reactor |
CA621190A (en) * | 1961-05-30 | Government Of Canada, As Represented By Atomic Energy Of Canada Limited | Neutron reactor | |
DE1126037B (en) * | 1960-11-25 | 1962-03-22 | Bbc Brown Boveri & Cie | Device for generating short-term neutron pulses |
US3136699A (en) * | 1946-02-21 | 1964-06-09 | Walter H Zinn | Neutronic reactor system |
US3172818A (en) * | 1965-03-09 | Heterogeneous nuclear reactors | ||
US3252867A (en) * | 1964-06-26 | 1966-05-24 | George H Conley | Long lifetime nuclear reactor |
US3258405A (en) * | 1961-08-22 | 1966-06-28 | Avco Corp | Nuclear reactor hydropulse system |
US3366545A (en) * | 1965-02-24 | 1968-01-30 | Ca Atomic Energy Ltd | Method of operating a plurality of reactors |
US3743575A (en) * | 1969-08-01 | 1973-07-03 | Hitachi Ltd | Method of heating a sample material to a high temperature by using a relatively low power nuclear reactor |
US4219384A (en) * | 1976-11-06 | 1980-08-26 | Hochtemperatur-Reaktorbau Gmbh | Driving apparatus for an absorber rod |
US4306414A (en) * | 1977-04-27 | 1981-12-22 | Kuhns John P | Method of performing work |
US4340970A (en) * | 1980-06-04 | 1982-07-20 | Friedrich Weinert | Power wheel |
US4435355A (en) * | 1980-06-04 | 1984-03-06 | Friederich Weinert | Power wheel with double action valve in conjunction with a drill bit |
US4462954A (en) * | 1982-01-11 | 1984-07-31 | Friedrich Weinert | Energy cell |
US5023044A (en) * | 1990-07-11 | 1991-06-11 | The Babcock & Wilcox Company | Nuclear reactor control assembly |
US5128093A (en) * | 1991-03-27 | 1992-07-07 | General Electric Company | Control rod drive hydraulic system |
US5200140A (en) * | 1992-02-12 | 1993-04-06 | General Electric Company | Cable control rod drive assembly |
US5557934A (en) * | 1994-12-20 | 1996-09-24 | Epoch Engineering, Inc. | Efficient energy conversion apparatus and method especially arranged to employ a stirling engine or alternately arranged to employ an internal combustion engine |
-
1999
- 1999-03-05 EP EP99917304A patent/EP1074024A4/en active Pending
- 1999-03-05 AU AU35456/99A patent/AU3545699A/en not_active Abandoned
- 1999-03-05 WO PCT/US1999/005448 patent/WO1999045545A1/en not_active Application Discontinuation
Patent Citations (20)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CA621190A (en) * | 1961-05-30 | Government Of Canada, As Represented By Atomic Energy Of Canada Limited | Neutron reactor | |
US3172818A (en) * | 1965-03-09 | Heterogeneous nuclear reactors | ||
US2812304A (en) * | 1946-01-09 | 1957-11-05 | John A Wheeler | Means for cooling reactors |
US3136699A (en) * | 1946-02-21 | 1964-06-09 | Walter H Zinn | Neutronic reactor system |
US2790761A (en) * | 1952-05-16 | 1957-04-30 | Leo A Ohlinger | Neutronic reactor |
US2875143A (en) * | 1956-07-16 | 1959-02-24 | Darol K Froman | Push-pull power reactor |
DE1126037B (en) * | 1960-11-25 | 1962-03-22 | Bbc Brown Boveri & Cie | Device for generating short-term neutron pulses |
US3258405A (en) * | 1961-08-22 | 1966-06-28 | Avco Corp | Nuclear reactor hydropulse system |
US3252867A (en) * | 1964-06-26 | 1966-05-24 | George H Conley | Long lifetime nuclear reactor |
US3366545A (en) * | 1965-02-24 | 1968-01-30 | Ca Atomic Energy Ltd | Method of operating a plurality of reactors |
US3743575A (en) * | 1969-08-01 | 1973-07-03 | Hitachi Ltd | Method of heating a sample material to a high temperature by using a relatively low power nuclear reactor |
US4219384A (en) * | 1976-11-06 | 1980-08-26 | Hochtemperatur-Reaktorbau Gmbh | Driving apparatus for an absorber rod |
US4306414A (en) * | 1977-04-27 | 1981-12-22 | Kuhns John P | Method of performing work |
US4340970A (en) * | 1980-06-04 | 1982-07-20 | Friedrich Weinert | Power wheel |
US4435355A (en) * | 1980-06-04 | 1984-03-06 | Friederich Weinert | Power wheel with double action valve in conjunction with a drill bit |
US4462954A (en) * | 1982-01-11 | 1984-07-31 | Friedrich Weinert | Energy cell |
US5023044A (en) * | 1990-07-11 | 1991-06-11 | The Babcock & Wilcox Company | Nuclear reactor control assembly |
US5128093A (en) * | 1991-03-27 | 1992-07-07 | General Electric Company | Control rod drive hydraulic system |
US5200140A (en) * | 1992-02-12 | 1993-04-06 | General Electric Company | Cable control rod drive assembly |
US5557934A (en) * | 1994-12-20 | 1996-09-24 | Epoch Engineering, Inc. | Efficient energy conversion apparatus and method especially arranged to employ a stirling engine or alternately arranged to employ an internal combustion engine |
Non-Patent Citations (1)
Title |
---|
See also references of EP1074024A4 * |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US9881706B2 (en) | 2013-08-23 | 2018-01-30 | Global Energy Research Associates, LLC | Nuclear powered rotary internal engine apparatus |
EP3308380A4 (en) * | 2015-04-09 | 2019-06-19 | Claudio Filippone | Transportable sub-critical modules for power generation and related methods |
CN105304147A (en) * | 2015-11-05 | 2016-02-03 | 罗浩源 | Nuclear aircraft based on micro engine |
Also Published As
Publication number | Publication date |
---|---|
AU3545699A (en) | 1999-09-20 |
WO1999045545A9 (en) | 2000-04-27 |
WO1999045545A8 (en) | 2000-03-02 |
EP1074024A1 (en) | 2001-02-07 |
EP1074024A4 (en) | 2001-07-25 |
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