WO2009148648A1 - Long life high-efficiency neutron generator - Google Patents
Long life high-efficiency neutron generator Download PDFInfo
- Publication number
- WO2009148648A1 WO2009148648A1 PCT/US2009/035600 US2009035600W WO2009148648A1 WO 2009148648 A1 WO2009148648 A1 WO 2009148648A1 US 2009035600 W US2009035600 W US 2009035600W WO 2009148648 A1 WO2009148648 A1 WO 2009148648A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- ion source
- target
- target material
- plasma
- magnetic field
- Prior art date
Links
Classifications
-
- H—ELECTRICITY
- H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
- H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
- H05H3/00—Production or acceleration of neutral particle beams, e.g. molecular or atomic beams
- H05H3/06—Generating neutron beams
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/19—Targets for producing thermonuclear fusion reactions, e.g. pellets for irradiation by laser or charged particle beams
-
- H—ELECTRICITY
- H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
- H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
- H05H6/00—Targets for producing nuclear reactions
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/02—Neutron sources
-
- 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
- Y02E30/10—Nuclear fusion reactors
Definitions
- Radioactive nuclear sources are currently used in industry in a variety of places, including on-line elemental analysis of mining, coal, and cement feedstocks, and sub-surface scanning (e.g. soil composition analysis and landmine detection).
- the traditional neutron source has been a radioisotope such as 252 Cf or Am-Be.
- Radioisotopes are always on, require shielding, limit types of analysis (e.g. no pulsing or time-of-flight), and pose a personnel hazard during manufacturing and assembly, as well as a security hazard due to threats of so-called "dirty bombs”.
- Neutrons can also be generated with conventional accelerator technology but these systems have large size and power consumption requirements.
- FIG. 1 The basic layout of a modern compact accelerator neutron source is shown in Figure 1.
- the standard hardware consists of: a high- voltage generator 1 ( ⁇ 100kV), a metal hydride target material 2 (usually titanium), one or more accelerator grids 3, an ion source assembly 4 (Penning or RF) and a gas-control reservoir 5 that often uses a hydrogen getter.
- Operation proceeds as follows: either pure deuterium (D-D system) or a deuterium-tritium (D-T system) mix of gas (up to 10 Ci of T) is introduced into the system at pressures around lOmTorr; a plasma is generated to provide ions that are extracted out of the source region and accelerated to -100 keV; these ions bombard the target 2 where they can undergo fusion reactions with other hydrogen isotopes embedded in the target 2. DD fusion reactions generate 2.45 MeV neutrons and the DT reaction makes 14 MeV neutrons. Exemplary systems can be operated continuously or in pulsed operation for time-of-flight measurements. [0004] There are several major suppliers of non-radioactive neutron generators, all using accelerator-target configurations.
- List prices range between $85-350K with the highest cost components being the high-voltage power supply, electrical feeds, and interconnects. Lifetime is typically limited by the degradation of the target material and the coating of insulators with best suppliers reporting -1000 hours for nominal output levels of 1x10 DD n/s and 1x10 DT n/s, and replacement target units range from $5-50K each. Currently, no suppliers have cost- effective high output (>1E8 n/s) DD systems.
- Neutron generators for industrial radioisotope replacement often use the DD fusion reaction because the 2.45-MeV DD neutrons are more easily applied to existing applications that use Cf 252 , which has an average neutron energy of 2.1 MeV.
- a DT generator On the basis of fusion cross section and reaction branching alone, a DT generator has a neutron production rate -100 times that of a DD generator, however, the shielding and moderation requirements for 14.1-MeV DT-generated neutrons compared to 2.45-MeV neutrons are much more severe, making DD more attractive for many market applications.
- aspects of the invention include a highly-innovative approach for a compact, high- efficiency, long-life fusion neutron generator (FNG) for applications such as enhanced neutron radiography, non-destructive testing, bulk material scanning using the testing process known as Prompt Gamma Neutron Activation Analysis (PGNAA), other NAA methods, and other analytical methods utilizing neutrons.
- FNG fusion neutron generator
- PNAA Prompt Gamma Neutron Activation Analysis
- Radioisotopes such as 252 Cf, are currently used in the academic and industrial markets, but are under increasing scrutiny due to homeland security concerns.
- FNG technologies are available in the marketplace, but are hampered by high cost, large size, low efficiency, and short lifetime, typically making them unsuitable for broad use.
- an innovation for the device as a whole results from the combination of a regenerable low-Z (low atomic number) target for long life and high efficiency with an RF ion source that allows compact and easy thermal management with long life.
- a regenerable low-Z (low atomic number) target for long life and high efficiency with an RF ion source that allows compact and easy thermal management with long life.
- These factors combine to increase yield and decrease cost.
- Improved efficiency and better thermal properties allow the source size to be decreased, allowing its use in applications that require small sources, such as small-diameter boreholes ( ⁇ 2 inches).
- Such a compact and inexpensive source could also be used in laboratory and academic settings for geoscience and other nondestructive testing applications, such as online bulk materials analysis (such as for coal and cement mining), soil analysis, borehole logging analysis, and security screening systems, and others.
- Radioactive neutron sources in industry could be replaced with FNGs in a wide variety of applications, improving safety and broadening the types of analysis that can be accomplished. Additionally, innovative designs have been made to combine the necessary components and subsystems of an FNG in highly efficient and cost-effective ways.
- Traditional ion sources such as a Penning ion source use active filaments or multiple plasma-contacting electrodes to create ionizations. These components eventually wear out, causing a system failure and limiting lifetime.
- Aspects of the present invention include a radio frequency (RF) or microwave ion source which uses no electrodes and has the advantage of generating high fractions of monatomic ions.
- RF radio frequency
- microwave ion source which uses no electrodes and has the advantage of generating high fractions of monatomic ions.
- An RF ion source uses a coiled, or shaped ribbon, antenna on the outside of the system wall/insulator that deposits electromagnetic power into the gas, causing ionizations, dissociations and plasma sustainment. While current FNGs bias their target to a large negative voltage to create the acceleration field, aspects of the invention use another inherent advantage of the RF ion source and raise the voltage of the plasma while maintaining the RF hardware and the target at or near ground potential. This is possible because the RF couples its energy through electromagnetic fields instead of physical electrodes in contact with the plasma. Using a grounded target resolves several design concerns, such as thermal control of the target and target diagnostics.
- the RF or microwave ion source also allows for relatively easy multi-source configurations where multiple ion beams can be extracted from a common plasma region to produce a mutli-point neutron source.
- pulsed operation In addition to continuous operation, several options exist for pulsed operation.
- One option is to pulse an extraction electrode. This has the benefit of requiring relatively low voltage pulses, but would still require a high- voltage pulse forming network.
- Another option is to use a pulse transformer to directly pulse the high- voltage power.
- a simple schematic of a transformer- based pulsing system is shown in Figure 7. This exemplary method has the advantage of allowing low-voltage pulse forming network elements and a low- voltage (lower cost) DC power supply.
- the use of beam-bunching electrodes can further shorten pulses of a system down to the nanosecond range.
- the choice of pulsing technique depends on the cost, size and the needs of the end-user. All of these techniques are capable of achieving pulse lengths in the range of 0.1- 10,000 ⁇ s with a corresponding broad range of repetition rates, depending on the duty factor of the pulse system.
- Figure 1 is a diagram of an exemplary modern compact accelerator neutron source, according to an aspect of the invention.
- Figure 2 is chart illustrating the properties of different components of an exemplary system, according to an aspect of the invention.
- Figure 3 is an exemplary neutron generator block diagram, according to an aspect of the invention.
- Figure 4 is an exemplary neutron generator, according to an aspect of the invention.
- Figure 5 is an exemplary neutron generator with RF ion source, according to an aspect of the invention.
- Figure 6 is an exemplary neutron generator modified for ECR ion source, according to an aspect of the invention.
- Figure 7 is an schematic drawing of an exemplary power pulser, according to an aspect of the invention.
- FIG. 3 shows the layout for the "neutron tube” core of a generic embodiment of the invention.
- a vacuum vessel 10 forms the main structure. Inside are the three primary electrodes: the ion source (anode) 11, neutron-producing target (cathode) 12, and electron suppressor electrode 13.
- the ion source power supply 14 creates AC, DC, or radio frequency/microwave power depending on the type of ion source 11 used.
- a non-evaporable getter 15 is used to control gas pressure via heating.
- the vacuum vessel 10 is a sealed tube made of a combination of conductor and insulator. If one end of the neutron tube is at low voltage, it can easily be made of conductive material facilitating fabrication and installation of electrical feedthroughs.
- Conductors used include primarily aluminum, stainless steel, copper, and kovar. Stainless steel and iron are minimized to reduce gamma signature in NAA applications. Glass, quartz, or alumina (or similar ceramic) can be used for insulated, high voltage areas.
- the outer diameter for this style of vacuum vessel 10 can range from 0.25" to 12".
- attached to the vacuum vessel 10, auxiliary to the neutron tube, can be a diagnostic pressure gauge 30, for example an ionization gauge. Electrical feedthroughs 31, 32, 33, 34, 35 allow voltages to be applied to or read from to the ion source 37, suppressor 13, target 12, diagnostic thermocouple 37 and getter 15, and also control other diagnostics and internal systems.
- a pump-out port 16 is included made of copper pinch-off tube, glass tube, or a mechanical valve 38. To fit these features within space constraints, vacuum- compatible tubing 39 may be used. Pump-out port 15 can be attached to metal or insulator sections of the vessel. In the case of systems assembled completely in a vacuum environment, a pump-out port may not be needed.
- the body of the vacuum vessel 10 is comprised of pre-made glass to metal or ceramic to metal seals that can be brazed or welded together using standard metalworking or glass working techniques, and/or have two sections affixed to each other with vacuum flanges 40 for easy assembly/disassembly, typically ranging in diameter from 1-1/3" to 12".
- the vessel 10 is pre-loaded with an appropriate amount of deuterium and/or tritium gas.
- an ion pump style of device can also be attached to the vessel to pump away helium and other contaminants after the getter 15 has temporarily pumped away the working gas.
- the ion source 36 is the anode 11 of the system that produces a plurality of ions that are accelerated into the target 12.
- the ion beam 43 is extracted from the ion source 36, goes through an opening in suppressor 13, and finally impinges on the target 12.
- the amount of extracted current should be from 10 nA/cm 2 to 1 kA/cm 2 .
- At the front of the ion source 36 is an extraction plane 41 with an open diameter typically between 1 mm and 80% of the ion source 36 diameter combined with electrode shapes 42 that customize the focusing of the extracted ion beam 43 to cover most or all of target 12.
- the extraction plane 41 may or may not contain a gridded extraction screen with a high percentage open area and grid spacing typically between 20 in-1 and 150 in-1, dependent on plasma properties.
- the system may or may not have an extraction bias electrode (not shown) positioned between the ion source 36 and the suppression electrode 13 to aid in extracting ion current.
- the ion beam 43 is shaped such that the energy density impinging on the target 12 is substantially uniform. This is beneficial for power/heat handling, neutron production efficiency, and target 12 lifetime.
- the type of ion source 36 used can be, but is not limited to, radio frequency (RF) using an RF antenna 44 and matching network system 45, electron-cyclotron resonance (ECR) using microwave generator 70 to make microwave energy 71, Penning (cold cathode) 4, field ionization, or spark gap.
- RF radio frequency
- ECR electron-cyclotron resonance
- the anode 11 region in vacuum may range from 1" to 12" long, filling either partially or completely the diameter of the vacuum vessel 10 containing it.
- the ion source 36 is comprised of a glass container 46 (to increase monatomic species fraction relative to quartz or alumina) inside of vacuum vessel 10 (to reduce the amount of sputtering, contamination, and ion-electron recombination compared to a steel or alumina container), RF antenna 44 (wrapped cylindrically around vacuum vessel 10 with 0.5 to 10 turns), magnets 47 (to make a strong, substantially uniform axial magnetic field of strength 10 Gauss to 10000 Gauss inside ion source 36 to minimize power losses from plasma- wall interactions), and RF matching network 45.
- Glass container 46 may be integral to vacuum vessel 10 (for example, see vacuum vessel 72).
- RF power input to the ion source 36 can range from 0.1 W to 10,000 W.
- the RF frequency can be in the range of 0.1 MHz to 1 GHz.
- Matching network 45 contains capacitors and/or inductors that can be of fixed and/or adjustable values, arranged in an "L" or "pi" configuration. The components can have the values fixed at the factory or be adjustable during operation with a stepper motor or similar system. To further fine-tune matching conditions in an assembled system, the frequency at which the RF generator 14 operates can be adjusted in sufficiently small increments.
- the components are chosen, arranged, tuned, and fixed in place in a relative arrangement similar to what is shown in Figure 4 to excite one or more modes to form and maximize plasma density and amount of extractable current, maximize monatomic species fraction in the ion beam 43, and optimize usage of RF power.
- the use of an ECR ion source can accomplish these objectives even more effectively.
- Typical values of frequency can range from 200 MHz to 20 GHz.
- Microwave energy can be applied to ion source with an external applicator including, but not limited to, a waveguide, dielectric window, or antenna launching structure.
- the magnetic field is shaped to create a zone of electron cyclotron resonance.
- the ion source 11 can be raised to a positive voltage or run at ground potential.
- the configuration is chosen to be appropriate for the requirements of pulsing, power level, size, and lifetime.
- the target 12 is near ground potential while the ion source 36 is raised to a high positive DC voltage.
- the electron suppressor electrode 13 works with the ion source extraction optics 41, 42 to shape the ion beam 43. It should be biased negative with respect to the target (cathode) electrode 12 by an amount ranging from 0 V to 10,000 V. It can be biased with a separate power supply 21, or be biased using a resistor or zener diode system attached to the target 12. It is sized and shaped such that field emission from the high voltage gradients is avoided.
- the outer diameter of the suppressor 13 should substantially fill the inner diameter of vacuum vessel 10; the opening at the center should be large enough to allow the ion beam 43 to pass through unobstructed, while not being so large so as to require a prohibitively large voltage difference between it and the target 12 to effectively suppress secondary electrons emitted from the target due to impinging ions.
- the one or more electrodes are arranged to shape an electric potential to cause a substantial fraction of ions from the ion source to collide with the target, to reduce electron losses to an anode electrode.
- the solid target (cathode) electrode 12 consists of a cooled metal substrate via coolant connections 33 (also used as an electric feed if a bias voltage is applied), usually stainless steel, nickel, copper or molybdenum, that is coated with a layer of hydrogen-absorbing material, such as lithium, titanium, or others to achieve useful neutron-producing reactions.
- a layer of hydrogen-absorbing material such as lithium, titanium, or others to achieve useful neutron-producing reactions.
- Low-Z materials are often preferable to increase efficiency.
- a target material may have at least one of the following properties: the average or effective atomic number of the target material is between 1 and 21 ; the target material can be regenerated in situ; the target material can be deposited in situ; the target material has the capability of causing secondary neutron-producing reactions with cross sections greater than 1 microbarn.
- the target may include hydrogen isotopes, lithium, lithium isotopes, lithium compounds including LiD, LiAlD 4 , and LiBD 4 , lithium alloys, and any mixture or combinations thereof.
- the target 12 can be maintained at ground potential or biased negative with an external power supply 17. Furthermore, the bias voltage between the suppressor and the target can be maintained by either connecting the suppressor to a negative voltage, or grounding it, and connecting the target to the suppressor through a zener diode, resistor, or other voltage regulation device.
- the size of the target 12 can be chosen appropriately for the application, power load, and lifetime needed.
- a substantially flat, circular shape is preferred, but other shapes, such as slanted, conical, or cylindrical, can be used to control sputtered material amounts and locations (both of source and destination) and to provide for unique neutron source emission areas/volumes.
- a circular target 12 for this style of device can range from 0.1" to 12" in diameter.
- a neutron tube 10 with two or more targets on either side of an ion source can be made so that two or more sources of neutrons are located inside of one device.
- Use of intentional sputtering and evaporation inside the vacuum vessel 10, 72 can have many benefits for system lifetime and efficiency.
- An attached thermocouple 37 or other means of measuring temperature can be used as a diagnostic while in operation.
- the cooling system 18 of the target 12 can be electrically isolated from the vacuum vessel 10, 72 in order to measure beam 43 current landing on the target 12 and for other diagnostic purposes.
- Active liquid cooling through channels 33 embedded in the target can be used for high power applications with either ambiently or actively cooled fluids. It is also possible to use a heat sink, exhausting to the surroundings.
- the location of the target can be anywhere beyond the suppressor electrode 13 in the path of the ion beam 43, viz. near the extreme end of the system to increase neutron flux on adjacent materials under test.
- the surface material of the target 12 can be deposited and/or refreshed in situ 3. Target 12 lifetime can be extended through use of regeneration.
- the target 12 material can also be chosen carefully to dictate the neutron output energy spectrum while still using deuterium and/or tritium as the working fuel.
- the gas reservoir 15 can be a simple titanium filament or a non-evaporable getter pump for increased vacuum vessel 10, 72 vacuum quality. It can be located in a low- voltage area, such as behind the target 12, to the side of the target 12, or behind or in the ion source region 36.
- An external power supply 19 runs ac or dc current through the device through an electrical feedthrough 35 to heat and control the gas reservoir's 15 temperature, thus controlling the pressure of the working gas in the vacuum vessel 10, 72. It is loaded with an appropriate amount of deuterium and or tritium gas to achieve operating pressures between 10 "5 Torr and 10 "2 Torr while maintaining enough of a reserve amount of gas to compensate for the effects of contamination and radioactive decay over time.
- High voltage power supplies 17, 20 are used to separate the ion source (anode) 11, 36 and target (cathode) 12 by fusion-relevant voltages, from 10 kV to greater than 500 kV. This can be accomplished with a positive voltage supply 20 connected to the anode 11, 36, a negative voltage supply 17 connected to the cathode 12, or both.
- the high voltages can be generated though a variety of means, such as with a traditional Cockcroft- Walton voltage multiplier 73, piezoelectric crystal transformer, or with pyroelectric crystal technology.
- the high voltage generation can be done in the generator system next to the neutron tube 10 or the high voltage can be transmitted to the neutron tube via an umbilical cable 48.
- ballast resistance 49 may be used, which can range in value from 10 k ⁇ to 10 M ⁇ .
- the external enclosure 50 contains the neutron tube 10 and associated feedthroughs, electronics, and power supplies. It is constructed from a conducting structural material such as aluminum or stainless steel to provide a ground shield around the entire system for safety and to prevent RF noise from affecting other equipment.
- the grounded enclosure 50 is filled with an insulating fluid 51 for high voltage standoff and cooling, such as mineral oil, transformer oil, SF 6 gas, or a fully fluorinated insulating fluid such as Fluorinert , which is sealed around the neutron tube 10 with seal 52.
- a control console may be included in the exemplary system that contains most or all of the needed support equipment in an enclosure or rack that protects the equipment and makes it accessible to the user for setting and monitoring operational parameters.
- the system controller should be housed here, which may be comprised of a personal computer, field-programmable gate array (FPGA), or other custom or standard circuitry. Analog and digital inputs and outputs allow the control system to communicate with the other pieces of equipment, viz. the ion source power supply (RF or microwave amplifier) 14, other power supplies as diagrammed in Figure 3, gas reservoir 15, and any applicable coolant systems 18.
- aspects of invention may include a plurality of diagnostic sensors selected from the group consisting of a particle detector, a current detector, a voltage detector, a resistivity monitor, a pressure gauge, a thermocouple, and a sputtering meter.
- the electrode area can maximized for a given neutron tube diameter to improve longevity and tube life.
- the control station is connected to the neutron tube 10 via a bundle of coaxial cables, wires, and tubing.
- a preferred embodiment is detailed in Figure 5.
- the vacuum envelope is a small diameter insulating tube 72 utilizing an RF-powered ion source 36 with magnet material 47.
- the ion source 36 is raised to high voltage with power supply 20 (depicted as a custom-built and sized Cockcroft- Walton voltage multiplier 73 located adjacent to the neutron tube 10 so that no high voltage umbilical cables 48 are required, and fed into vacuum vessel 72 with feedthrough 74 embedded in vacuum vessel 72 to bias beam-shaping electrodes (41, 42)) and the flat, circular target 12 is at ground potential.
- the suppressor 13 is biased via feedthrough 75 embedded in vacuum vessel 72.
- An advanced getter material 15 is loaded with D and/or T and uses a closed- loop control system 19 to maintain stable gas pressure in the vacuum vessel 72.
- the target 12 comprised of a thin layer of lithium to maximize efficiency 2 and customize the neutron energy spectrum 5, is located on a cooled substrate made of a material such as nickel or molybdenum and can be regenerated 4 with heat from the ion beam 43 and through an in-situ evaporation process 3 that does not require the neutron tube 72 to be opened.
- the target 12 is located near the extreme end of the system to place maximum neutron flux on the objects under test.
- a grounded target 12 can be directly heatsinked to the external enclosure 50 to efficiently transport heat generated by the ion beam interaction with the target to the surrounding environment.
- the external enclosure 50 is made of aluminum to minimize NAA signals; similarly, use of carbon steel and stainless steel in general is minimized.
- the external enclosure 50 is filled and sealed with a fully fluorinated insulating and cooling fluid to avoid neutron moderation and absorption by hydrogen.
- Figure 6 shows a preferred embodiment modified to use an ECR-type ion source 36 using microwave generator 70 to make microwave energy 71, exciting gas molecules to create ionizations.
- Basic layouts of components auxiliary to neutron tube (10, 72) can be readily adjusted for the device to fit within the size and shape constraints of a given application.
- Aspects of the invention include a neutron generator having an RF ion source. To achieve high atomic fractions in such neutron generators (e.g. >50%) inductively coupled plasma discharges are often used. Traditionally these require kilowatt-level power for hydrogen discharges due to the high mobility of hydrogen ions in the plasma. As a result intense heating and thermal cooling issues make compact devices difficult and expensive to engineer.
- aspects of the invention include an approach to design the plasma source cavity to encourage dissociation of molecular hydrogen gas through plasma interaction while maintaining a high degree of atomic hydrogen trapping or confinement within the plasma region for subsequent ionization. This can be accomplished by using a low recombination rate surface materials exposed to the plasma and high geometric trapping design of the plasma source region. Additionally , surfaces can be treated to reduce their surface recombination properties by a variety of techniques including but not limited to, chemical etch, material deposition, baking, coating, and plasma treatment.
- the plasma source region is crafted with low-recombination material surfaces and an exit aperture such that dissociated hydrogen atoms will bounce around within the plasma source volume with a high degree of confinement until ionization near the exit aperture for ion beam extraction. Optimization of this neutral atomic trapping can be done by shaping the ion source.
- RF energy can be efficiently transferred into the plasma near the exit aperture using the magnetic mirror effect.
- RF plasma pumping can drive electrons into a high magnetic field location and transfer axial energy into radial energy. Electrons with high radial energy ionize and dissociate hydrogen rapidly while low axial velocity increases local density in the high B field region and produce a high-quality ion beam.
- the RF antenna is located in the region of lower magnetic field such that electrons are accelerated into the higher B section with the RF or electromagnetic field.
- the applied RF frequency can be adjusted to maximize plasma power deposition into the high field region in relation to the electron bounce frequency between the RF antenna region and the high field region.
- the ion source exit aperture is located near this region to source high currents. Combined with low- recombination materials and geometric trapping, high atomic hydrogen ion fractions and beam currents can be obtained with low input power levels. For a 1 -inch diameter tube, currents in excess of ImA have been obtained for power levels of less than 5 W with good atomic to molecular fractions.
- the design of the magnetic mirror, B field shape and plasma source volume and ion beam extraction aperture can be optimized for different neutron generator applications, e.g. small diameter for oil-well logging applications, high current for neutron radiography or cargo inspection applications, etc. Adjusting the source profile affects the beam profile projected onto the target. This is important for heating purposes and it is desired to have a uniform target loading.
- the magnetic mirror is adjusted such that the ion source exit aperture magnetic field is close to that of the field in the RF source region to produce a highly- uniform beam at the target location.
- Another embodiment of invention may include one ion source that generates ions that are accelerated and collide with one or more target materials each at a different target location.
- a further embodiment may include a negative ion source.
- a state-of-the-art high-efficiency ion source using a helicon RF plasma produces 8.ImA of ion current using 1.24kW of RF power for an efficiency of 6.5 microamperes per Watt of RF power .
- An aspect of the invention produces at least 10 microamperes of ion current per Watt of RF power. By enhancing the neutral atomic species trapping in the ion source, 10 microamperes of atomic ion current per Watt of RF power can also be attained.
Abstract
Description
Claims
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN200980110297.4A CN101978429B (en) | 2008-02-27 | 2009-02-27 | Long life high efficiency neutron generator |
US12/919,912 US9607720B2 (en) | 2008-02-27 | 2009-02-27 | Long life high efficiency neutron generator |
AU2009255564A AU2009255564B2 (en) | 2008-02-27 | 2009-02-27 | Long life high-efficiency neutron generator |
EP09758811.5A EP2257948B1 (en) | 2008-02-27 | 2009-02-27 | Long life high-efficiency neutron generator and corresponding method |
US15/469,926 US10366795B2 (en) | 2008-02-27 | 2017-03-27 | Long-life high-efficiency neutron generator |
Applications Claiming Priority (10)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US3191608P | 2008-02-27 | 2008-02-27 | |
US3189908P | 2008-02-27 | 2008-02-27 | |
US3192108P | 2008-02-27 | 2008-02-27 | |
US3190808P | 2008-02-27 | 2008-02-27 | |
US3191208P | 2008-02-27 | 2008-02-27 | |
US61/031,916 | 2008-02-27 | ||
US61/031,921 | 2008-02-27 | ||
US61/031,912 | 2008-02-27 | ||
US61/031,908 | 2008-02-27 | ||
US61/031,899 | 2008-02-27 |
Related Child Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US12/919,912 A-371-Of-International US9607720B2 (en) | 2008-02-27 | 2009-02-27 | Long life high efficiency neutron generator |
US15/469,926 Continuation US10366795B2 (en) | 2008-02-27 | 2017-03-27 | Long-life high-efficiency neutron generator |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2009148648A1 true WO2009148648A1 (en) | 2009-12-10 |
Family
ID=41016488
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/US2009/035595 WO2009108906A1 (en) | 2008-02-27 | 2009-02-27 | Method and system for in situ depositon and regeneration of high efficiency target materials for long life nuclear reaction devices |
PCT/US2009/035600 WO2009148648A1 (en) | 2008-02-27 | 2009-02-27 | Long life high-efficiency neutron generator |
Family Applications Before (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/US2009/035595 WO2009108906A1 (en) | 2008-02-27 | 2009-02-27 | Method and system for in situ depositon and regeneration of high efficiency target materials for long life nuclear reaction devices |
Country Status (6)
Country | Link |
---|---|
US (3) | US9008256B2 (en) |
EP (2) | EP2263237B1 (en) |
CN (2) | CN101990686B (en) |
AU (2) | AU2009219148B2 (en) |
WO (2) | WO2009108906A1 (en) |
ZA (1) | ZA201006271B (en) |
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2341525A3 (en) * | 2009-12-30 | 2012-03-07 | FEI Company | Plasma source for charged particle beam system |
CN102548181A (en) * | 2012-01-19 | 2012-07-04 | 哈尔滨市源盛达电子技术有限公司 | Small-diameter radio-frequency drive deuterium-deuterium neutron pipe |
WO2012112206A1 (en) * | 2011-02-18 | 2012-08-23 | Highfuels, Inc. | Method and apparatus for intermediate controlled fusion processes |
US8642974B2 (en) | 2009-12-30 | 2014-02-04 | Fei Company | Encapsulation of electrodes in solid media for use in conjunction with fluid high voltage isolation |
US8987678B2 (en) | 2009-12-30 | 2015-03-24 | Fei Company | Encapsulation of electrodes in solid media |
WO2017082890A1 (en) * | 2015-11-11 | 2017-05-18 | Halliburton Energy Services, Inc. | Long-lifetime, high-yield, fast neutrons source |
US9818584B2 (en) | 2011-10-19 | 2017-11-14 | Fei Company | Internal split faraday shield for a plasma source |
CN107708284A (en) * | 2017-09-11 | 2018-02-16 | 中国工程物理研究院核物理与化学研究所 | A kind of deuterium deuterium accelerator for neutron production target chamber |
US10438713B2 (en) | 2015-11-16 | 2019-10-08 | Halliburton Energy Services, Inc. | High output accelerator neutron source |
Families Citing this family (87)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN101990686B (en) | 2008-02-27 | 2015-11-25 | 星火工业有限公司 | The in-situ deposition of the efficient target of long-life nuclear reaction device and renovation process and system |
PL2294582T3 (en) | 2008-05-02 | 2019-02-28 | Shine Medical Technologies, Inc. | Device and method for producing medical isotopes |
US9723704B2 (en) * | 2008-08-12 | 2017-08-01 | Lawrence Livermore National Security, Llc | Neutron interrogation systems using pyroelectric crystals and methods of preparation thereof |
US8624502B2 (en) * | 2009-05-15 | 2014-01-07 | Alpha Source Llc | Particle beam source apparatus, system and method |
CA2781094A1 (en) | 2009-11-16 | 2011-05-19 | Schlumberger Canada Limited | Compact radiation generator |
US9793084B2 (en) | 2009-11-16 | 2017-10-17 | Schlumberger Technology Corporation | Floating intermediate electrode configuration for downhole nuclear radiation generator |
US9155185B2 (en) * | 2009-11-16 | 2015-10-06 | Schlumberger Technology Corporation | Electrode configuration for downhole nuclear radiation generator |
WO2012003009A2 (en) | 2010-01-28 | 2012-01-05 | Shine Medical Technologies, Inc. | Segmented reaction chamber for radioisotope production |
JP5041495B2 (en) * | 2010-11-01 | 2012-10-03 | シャープ株式会社 | Ion generator |
US10734126B2 (en) | 2011-04-28 | 2020-08-04 | SHINE Medical Technologies, LLC | Methods of separating medical isotopes from uranium solutions |
JP5747308B2 (en) * | 2011-06-27 | 2015-07-15 | 株式会社Cics | Lithium target automatic regeneration device, neutron source, and lithium target automatic regeneration method |
AU2012283031A1 (en) * | 2011-07-08 | 2013-12-19 | Conocophillips Company | Electromagnetic depth/orientation detection tool and methods thereof |
US9378956B2 (en) * | 2011-08-25 | 2016-06-28 | Aeroflex Colorado Springs Inc. | Wafer structure for electronic integrated circuit manufacturing |
US9378955B2 (en) | 2011-08-25 | 2016-06-28 | Aeroflex Colorado Springs Inc. | Wafer structure for electronic integrated circuit manufacturing |
US9396947B2 (en) | 2011-08-25 | 2016-07-19 | Aeroflex Colorado Springs Inc. | Wafer structure for electronic integrated circuit manufacturing |
WO2013040525A1 (en) * | 2011-09-15 | 2013-03-21 | Schlumberger Canada Limited | Target extender in radiation generator |
CN103306663B (en) * | 2012-03-06 | 2016-01-27 | 中国原子能科学研究院 | Uranium ore logging method |
WO2013133342A1 (en) * | 2012-03-06 | 2013-09-12 | 独立行政法人理化学研究所 | Neutron generation source, and neutron generation device |
JP5992715B2 (en) * | 2012-04-05 | 2016-09-14 | シャープ株式会社 | Ion generator |
IN2014DN09137A (en) | 2012-04-05 | 2015-05-22 | Shine Medical Technologies Inc | |
DK3461240T3 (en) * | 2012-04-27 | 2022-12-12 | Triumf Inc | METHODS, SYSTEMS, AND APPARATUS FOR CYCLOTRON PRODUCTION OF TECHNETIUM-99M |
US9392681B2 (en) | 2012-08-03 | 2016-07-12 | Schlumberger Technology Corporation | Borehole power amplifier |
US20140035588A1 (en) * | 2012-08-03 | 2014-02-06 | Schlumberger Technology Corporation | Borehole particle accelerator |
US9484176B2 (en) * | 2012-09-10 | 2016-11-01 | Thomas Schenkel | Advanced penning ion source |
AU2012390330A1 (en) * | 2012-09-18 | 2015-03-19 | Halliburton Energy Services, Inc. | Method and system of a neutron tube |
US9147550B2 (en) * | 2012-12-03 | 2015-09-29 | Advanced Ion Beam Technology, Inc. | Gas mixture method and apparatus for generating ion beam |
US9129770B2 (en) | 2013-03-14 | 2015-09-08 | Schlumberger Technology Corporation | Ion source having negatively biased extractor |
WO2014145726A1 (en) | 2013-03-15 | 2014-09-18 | Starfire Industries Llc | Compact high-voltage plasma source for neutron generation |
WO2014146008A2 (en) | 2013-03-15 | 2014-09-18 | Starfire Industries Llc | Scalable multi-role surface-wave plasma generator |
CN103200759A (en) * | 2013-03-17 | 2013-07-10 | 东北师范大学 | Heat dissipation mechanism of high-yield neutron generator |
CN103313503B (en) * | 2013-05-19 | 2016-12-28 | 中国科学院近代物理研究所 | Solid spallation target for Accelerator Driven Subcritical nuclear power system |
WO2015047473A2 (en) * | 2013-06-14 | 2015-04-02 | The Curators Of The University Of Missouri | Low-power, compact piezoelectric particle emission |
JP6355011B2 (en) * | 2013-11-12 | 2018-07-11 | 田中貴金属工業株式会社 | Neutron generation target |
CN104033148B (en) * | 2013-12-09 | 2017-02-22 | 哈尔滨市源盛达电子技术有限公司 | Manufacture method of ceramic ring with insulated isolation groove for small-diameter neutron tubes |
US9472370B2 (en) * | 2013-12-16 | 2016-10-18 | Schlumberger Technology Corporation | Neutron generator having multiple extractors with independently selectable potentials |
US9915753B2 (en) | 2013-12-19 | 2018-03-13 | Schlumberger Technology Corporation | Electrically operated radiation source operating power, reliability and life management systems and methods |
WO2015183769A1 (en) * | 2014-05-26 | 2015-12-03 | Goldberg Adam S | Nuclear fusion using high energy charged particle convergence at a target cathode |
US20170301411A1 (en) * | 2014-06-04 | 2017-10-19 | Hydrogen Fusion Systems, Llc | Nuclear Fusion of Common Hydrogen |
CN104244560B (en) * | 2014-07-16 | 2017-04-05 | 中国工程物理研究院核物理与化学研究所 | Small-sized high yield deuterium deuterium accelerator for neutron production |
CN104093261B (en) * | 2014-07-16 | 2017-02-15 | 中国工程物理研究院核物理与化学研究所 | Helium processing device of high yield neutron generator |
CN104093260A (en) * | 2014-07-16 | 2014-10-08 | 中国工程物理研究院核物理与化学研究所 | High potential terminal radiating device of high yield neutron generator |
CN105407622B (en) * | 2014-09-11 | 2018-04-20 | 邱慈云 | The target of nucleic bombardment, bombardment system and method |
CN107148652B (en) * | 2014-09-16 | 2021-02-12 | 阿格尼能源有限公司 | Alwen wave rotary non-linear inertial confinement reactor |
CN104363693B (en) * | 2014-09-17 | 2017-06-06 | 东北师范大学 | Plane radio-frequency ion source setl-target neutron tube |
WO2016060867A1 (en) * | 2014-10-15 | 2016-04-21 | Gtat Corporation | Generating neutrons using a rotating neutron source material |
WO2016088845A1 (en) * | 2014-12-04 | 2016-06-09 | 株式会社カネカ | Interlayer thermally bondable graphite sheet for high vacuum |
CN104966448B (en) * | 2015-07-09 | 2018-04-27 | 东北师范大学 | Radio frequency neutron tube ion gun line draws tabletop experiments platform |
US10128082B2 (en) * | 2015-07-24 | 2018-11-13 | Varian Semiconductor Equipment Associates, Inc. | Apparatus and techniques to treat substrates using directional plasma and point of use chemistry |
CN109589503A (en) * | 2015-09-11 | 2019-04-09 | 南京中硼联康医疗科技有限公司 | Discharging plasma sintering equipment and sintering process |
CN105223864A (en) * | 2015-09-23 | 2016-01-06 | 东北师范大学 | Electricity controllable pulse formula neutron generator control desk |
CN105407621B (en) * | 2015-11-13 | 2018-01-16 | 兰州大学 | A kind of compact D D accelerators for neutron production |
EP3347570A4 (en) * | 2015-12-10 | 2019-05-15 | Halliburton Energy Services, Inc. | Downhole field ionization neutron generator |
WO2017192834A1 (en) * | 2016-05-04 | 2017-11-09 | Cornell University | Wafer-based charged particle accelerator, wafer components, methods, and applications |
CN109478610B (en) * | 2016-05-23 | 2022-03-18 | 丹尼尔.H.迪克斯 | Method and apparatus for sealing of metal |
RU2639320C1 (en) * | 2016-09-16 | 2017-12-21 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Device for electrical connecting intrachamber components with vacuum case of thermonuclear reactor |
JP6831921B2 (en) * | 2016-10-31 | 2021-02-17 | 南京中硼▲聯▼康医▲療▼科技有限公司Neuboron Medtech Ltd. | Neutron capture therapy system |
CN106507576A (en) * | 2016-11-04 | 2017-03-15 | 中国工程物理研究院流体物理研究所 | The ionogenic ion filter device of metal hydride, method and neutron generator |
CN106455282A (en) * | 2016-11-04 | 2017-02-22 | 中国工程物理研究院流体物理研究所 | Ion filtration method, grid with ion filtration function and neutron generator |
US10316621B2 (en) * | 2016-12-15 | 2019-06-11 | Schlumberger Technology Corporation | Downhole tool power balancing |
CN108934120B (en) * | 2017-05-26 | 2024-04-12 | 南京中硼联康医疗科技有限公司 | Target for neutron ray generating device and neutron capturing treatment system |
JP7224290B2 (en) | 2017-01-18 | 2023-02-17 | フェニックス エルエルシー | High power ion beam generator system and method |
CN107027236B (en) * | 2017-05-27 | 2023-07-25 | 中国工程物理研究院流体物理研究所 | Neutron generator |
NZ760149A (en) * | 2017-06-05 | 2022-09-30 | Takao Sakase | Method and system for surface modification of substrate for ion beam target |
US10462893B2 (en) | 2017-06-05 | 2019-10-29 | Neutron Therapeutics, Inc. | Method and system for surface modification of substrate for ion beam target |
CN107331430B (en) * | 2017-08-10 | 2023-04-28 | 海默科技(集团)股份有限公司 | Double-source double-energy-level ray source bin of multiphase flow phase fraction measuring device |
US11675102B2 (en) * | 2018-02-26 | 2023-06-13 | Starfire Industries Llc | Associated particle detection for performing neutron flux calibration and imaging |
US10955582B2 (en) | 2018-02-26 | 2021-03-23 | Starfire Industries Llc | Azimuthal associated particle imaging neutron generator for neutron x-ray inspection system gamma imaging for oil and gas technologies |
CN108492903B (en) * | 2018-04-17 | 2020-01-10 | 东莞理工学院 | Interchangeable neutron pipe's exchange system |
CN108806816B (en) * | 2018-04-18 | 2019-08-06 | 中国科学院合肥物质科学研究院 | A kind of neutron energy spectrum control accurate technology and device |
EP3803902A4 (en) * | 2018-06-03 | 2022-06-22 | Metzler, Florian | System and method for phonon-mediated excitation and de-excitation of nuclear states |
CN109256233B (en) * | 2018-07-26 | 2020-12-22 | 东莞材料基因高等理工研究院 | A pipe auto-change over device for neutron scattering spectrometer |
CN109045487A (en) * | 2018-09-03 | 2018-12-21 | 东莞东阳光高能医疗设备有限公司 | A kind of neutron capture therapy system based on proton linac |
WO2020081694A1 (en) * | 2018-10-16 | 2020-04-23 | Philip Teague | Combined thermal and voltage transfer system for an x-ray source |
CN109496051A (en) * | 2018-12-21 | 2019-03-19 | 北京中百源国际科技创新研究有限公司 | It is a kind of for increasing the slowing down device of low number of neutrons |
CN109831868B (en) * | 2019-02-14 | 2020-01-14 | 兰州大学 | Small-size deuterium neutron generator of integration |
CN110320564B (en) * | 2019-06-03 | 2021-02-23 | 中国工程物理研究院核物理与化学研究所 | Neutron backscattering plastic landmine imaging method based on probability matrix traceability |
CN112343780B (en) * | 2019-08-09 | 2021-08-13 | 哈尔滨工业大学 | Microwave coaxial resonance cusped field thruster |
CN111093312B (en) * | 2019-12-30 | 2021-11-16 | 北京应用物理与计算数学研究所 | Double-layer hole ion leading-out and accelerating device |
CN111741583B (en) * | 2020-05-26 | 2021-09-28 | 中国原子能科学研究院 | Integrated desktop type neutron generator |
CN111642053B (en) * | 2020-05-26 | 2021-06-29 | 中国原子能科学研究院 | Compact flow guide structure for high-voltage unit of neutron generator |
CN111712032B (en) * | 2020-05-26 | 2021-05-04 | 中国原子能科学研究院 | Self-shielding DD neutron generator |
CN111698822B (en) * | 2020-05-26 | 2021-07-16 | 中国原子能科学研究院 | Vertical neutron generator |
CN111741584B (en) * | 2020-05-26 | 2021-12-28 | 中国原子能科学研究院 | D+Ion source |
RU2020124384A (en) * | 2020-07-23 | 2022-01-26 | Таэ Текнолоджиз, Инк. | SYSTEMS, DEVICES AND METHODS FOR REDUCING DEFORMATION AND STRENGTH IN METAL BODIES |
CN112420235A (en) * | 2020-10-26 | 2021-02-26 | 南京即衡科技发展有限公司 | Combinable controllable Am-Be neutron source device |
TWI758921B (en) * | 2020-10-27 | 2022-03-21 | 行政院原子能委員會核能研究所 | Neutron generating method and neutron generator |
US11574788B1 (en) * | 2021-10-08 | 2023-02-07 | Adelphi Technology, Inc. | Ion source having a magnetic field translatable along an axis of the source |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3664960A (en) | 1968-02-02 | 1972-05-23 | Nat Res Dev | Control circuit for neutron generator tube |
US20030006708A1 (en) * | 2001-05-17 | 2003-01-09 | Ka-Ngo Leung | Microwave ion source |
US20030152186A1 (en) * | 2002-01-28 | 2003-08-14 | Jurczyk Brian E. | Gas-target neutron generation and applications |
US20030234355A1 (en) * | 2002-02-06 | 2003-12-25 | Ka-Ngo Leung | Neutron tubes |
Family Cites Families (20)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2951945A (en) * | 1954-05-26 | 1960-09-06 | Schlumberger Well Surv Corp | Renewable target |
US2943239A (en) * | 1954-06-29 | 1960-06-28 | Schlumberger Well Surv Corp | Method and apparatus for renewing targets |
US3417245A (en) * | 1962-10-23 | 1968-12-17 | Kernforschung Gmbh Ges Fuer | Neutron generating apparatus |
GB981297A (en) * | 1963-01-14 | 1965-01-20 | Atomic Energy Authority Uk | Apparatus for carrying out a nuclear reaction |
US3393316A (en) | 1964-04-23 | 1968-07-16 | Kaman Corp | Self-rectified positive ion accelerator and neutron generator |
FR1481123A (en) | 1966-03-11 | 1967-05-19 | Commissariat Energie Atomique | Process for the production, acceleration and interaction of beams of charged particles and device for carrying out said process |
GB1325685A (en) * | 1969-12-23 | 1973-08-08 | Nat Res Dev | Neutron generators |
US3779864A (en) * | 1971-10-29 | 1973-12-18 | Atomic Energy Commission | External control of ion waves in a plasma by high frequency fields |
US4309249A (en) | 1979-10-04 | 1982-01-05 | The United States Of America As Represented By The United States Department Of Energy | Neutron source, linear-accelerator fuel enricher and regenerator and associated methods |
US4568509A (en) * | 1980-10-10 | 1986-02-04 | Cvijanovich George B | Ion beam device |
FR2630251B1 (en) * | 1988-04-19 | 1990-08-17 | Realisations Nucleaires Et | HIGH-FLOW NEUTRON GENERATOR WITH LONG LIFE TARGET |
FR2635912A1 (en) * | 1988-08-26 | 1990-03-02 | Sodern | REGENERABLE SEALED ELECTRONIC TUBE DEVICE |
US5293410A (en) * | 1991-11-27 | 1994-03-08 | Schlumberger Technology Corporation | Neutron generator |
US5970108A (en) * | 1998-01-30 | 1999-10-19 | Drexler; Jerome | Method and apparatus for detecting high velocity alpha particles having captured electrons |
US20020150193A1 (en) * | 2001-03-16 | 2002-10-17 | Ka-Ngo Leung | Compact high flux neutron generator |
US8090071B2 (en) * | 2001-08-08 | 2012-01-03 | James Robert DeLuze | Apparatus for hot fusion of fusion-reactive gases |
US7200198B2 (en) * | 2002-05-21 | 2007-04-03 | Duke University | Recirculating target and method for producing radionuclide |
US20070237281A1 (en) * | 2005-08-30 | 2007-10-11 | Scientific Drilling International | Neutron generator tube having reduced internal voltage gradients and longer lifetime |
JP2007328965A (en) * | 2006-06-07 | 2007-12-20 | Univ Nagoya | Ion generator and neutron generator |
CN101990686B (en) | 2008-02-27 | 2015-11-25 | 星火工业有限公司 | The in-situ deposition of the efficient target of long-life nuclear reaction device and renovation process and system |
-
2009
- 2009-02-27 CN CN200980112592.3A patent/CN101990686B/en active Active
- 2009-02-27 EP EP09713677.4A patent/EP2263237B1/en active Active
- 2009-02-27 WO PCT/US2009/035595 patent/WO2009108906A1/en active Application Filing
- 2009-02-27 US US12/919,890 patent/US9008256B2/en active Active
- 2009-02-27 US US12/919,912 patent/US9607720B2/en active Active
- 2009-02-27 EP EP09758811.5A patent/EP2257948B1/en active Active
- 2009-02-27 AU AU2009219148A patent/AU2009219148B2/en active Active
- 2009-02-27 WO PCT/US2009/035600 patent/WO2009148648A1/en active Application Filing
- 2009-02-27 AU AU2009255564A patent/AU2009255564B2/en active Active
- 2009-02-27 CN CN200980110297.4A patent/CN101978429B/en active Active
-
2010
- 2010-09-01 ZA ZA2010/06271A patent/ZA201006271B/en unknown
-
2017
- 2017-03-27 US US15/469,926 patent/US10366795B2/en active Active
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3664960A (en) | 1968-02-02 | 1972-05-23 | Nat Res Dev | Control circuit for neutron generator tube |
US20030006708A1 (en) * | 2001-05-17 | 2003-01-09 | Ka-Ngo Leung | Microwave ion source |
US20030152186A1 (en) * | 2002-01-28 | 2003-08-14 | Jurczyk Brian E. | Gas-target neutron generation and applications |
US20030234355A1 (en) * | 2002-02-06 | 2003-12-25 | Ka-Ngo Leung | Neutron tubes |
Cited By (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2341525A3 (en) * | 2009-12-30 | 2012-03-07 | FEI Company | Plasma source for charged particle beam system |
US8642974B2 (en) | 2009-12-30 | 2014-02-04 | Fei Company | Encapsulation of electrodes in solid media for use in conjunction with fluid high voltage isolation |
US8987678B2 (en) | 2009-12-30 | 2015-03-24 | Fei Company | Encapsulation of electrodes in solid media |
US9196451B2 (en) | 2009-12-30 | 2015-11-24 | Fei Company | Plasma source for charged particle beam system |
WO2012112206A1 (en) * | 2011-02-18 | 2012-08-23 | Highfuels, Inc. | Method and apparatus for intermediate controlled fusion processes |
US9591735B2 (en) | 2011-06-21 | 2017-03-07 | Fei Company | High voltage isolation of an inductively coupled plasma ion source with a liquid that is not actively pumped |
US9818584B2 (en) | 2011-10-19 | 2017-11-14 | Fei Company | Internal split faraday shield for a plasma source |
CN102548181B (en) * | 2012-01-19 | 2016-01-06 | 哈尔滨市源盛达电子技术有限公司 | Small-diameter radio-frequency drive deuterium-deuterium neutron pipe |
CN102548181A (en) * | 2012-01-19 | 2012-07-04 | 哈尔滨市源盛达电子技术有限公司 | Small-diameter radio-frequency drive deuterium-deuterium neutron pipe |
WO2017082890A1 (en) * | 2015-11-11 | 2017-05-18 | Halliburton Energy Services, Inc. | Long-lifetime, high-yield, fast neutrons source |
US10288763B2 (en) | 2015-11-11 | 2019-05-14 | Halliburton Energy Services, Inc. | Long-lifetime, high-yield, fast neutrons source |
US10502861B2 (en) | 2015-11-11 | 2019-12-10 | Halliburton Energy Services, Inc. | Long-lifetime, high-yield, fast neutrons source |
US10438713B2 (en) | 2015-11-16 | 2019-10-08 | Halliburton Energy Services, Inc. | High output accelerator neutron source |
CN107708284A (en) * | 2017-09-11 | 2018-02-16 | 中国工程物理研究院核物理与化学研究所 | A kind of deuterium deuterium accelerator for neutron production target chamber |
Also Published As
Publication number | Publication date |
---|---|
EP2263237A1 (en) | 2010-12-22 |
US20110044418A1 (en) | 2011-02-24 |
EP2257948A4 (en) | 2014-01-08 |
CN101990686B (en) | 2015-11-25 |
US20170301410A1 (en) | 2017-10-19 |
US9607720B2 (en) | 2017-03-28 |
US20110091000A1 (en) | 2011-04-21 |
AU2009255564A1 (en) | 2009-12-10 |
EP2263237B1 (en) | 2017-08-23 |
WO2009108906A1 (en) | 2009-09-03 |
AU2009219148B2 (en) | 2013-07-25 |
AU2009255564B2 (en) | 2013-06-13 |
CN101990686A (en) | 2011-03-23 |
CN101978429B (en) | 2015-04-29 |
CN101978429A (en) | 2011-02-16 |
AU2009219148A1 (en) | 2009-09-03 |
US10366795B2 (en) | 2019-07-30 |
EP2257948B1 (en) | 2018-03-28 |
ZA201006271B (en) | 2011-10-26 |
EP2257948A1 (en) | 2010-12-08 |
EP2263237A4 (en) | 2014-01-08 |
US9008256B2 (en) | 2015-04-14 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US10366795B2 (en) | Long-life high-efficiency neutron generator | |
US20070237281A1 (en) | Neutron generator tube having reduced internal voltage gradients and longer lifetime | |
Ivanov et al. | Radio frequency ion source for plasma diagnostics in magnetic fusion experiments | |
Mertzig et al. | A high-compression electron gun for C6+ production: concept, simulations and mechanical design | |
Reijonen | Neutron generators developed at LBNL for homeland security and imaging applications | |
Belchenko et al. | Studies of ion and neutral beam physics and technology at the Budker Institute of Nuclear Physics, SB RAS | |
US8440981B2 (en) | Compact pyroelectric sealed electron beam | |
US5675606A (en) | Solenoid and monocusp ion source | |
Dudnikov | Surface-plasma method for the production of negative ion beams | |
JP2008202942A (en) | Fusion neutron generator | |
US8971473B2 (en) | Plasma driven neutron/gamma generator | |
Bures et al. | A plasma focus electronic neutron generator | |
US9484176B2 (en) | Advanced penning ion source | |
Froese | The TITAN electron beam ion trap: Assembly, characterization, and first tests | |
US3302026A (en) | Ion source neutron generator having magnetically stabilized plasma | |
Piefer et al. | Design of an ion source for 3He Fusion in a low pressure IEC device | |
Lawrie | Understanding the plasma and improving extraction of the ISIS Penning H-ions source | |
Gobin et al. | Two approaches for H− ion production with 2.45 GHz ion sources | |
Schachter et al. | On the physics of metal–dielectric structures in ECR ion sources | |
Ascası́bar et al. | Overview of TJ-II flexible heliac results | |
Rauner | Efficiency of RF plasma generation for fusion relevant ion sources | |
Dudnikov | Surface Plasma Production of Negative Ions | |
Perkins | A compact ion source for intense neutron generation | |
del Pozo Rodriguez | Investigation and optimisation of a plasma cathode electron beam gun for material processing applications | |
Neben | Perturbative Measurements of Electron Cyclotron Resonance Ion Source Plasmas |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
WWE | Wipo information: entry into national phase |
Ref document number: 200980110297.4 Country of ref document: CN |
|
121 | Ep: the epo has been informed by wipo that ep was designated in this application |
Ref document number: 09758811 Country of ref document: EP Kind code of ref document: A1 |
|
WWE | Wipo information: entry into national phase |
Ref document number: 2009255564 Country of ref document: AU |
|
NENP | Non-entry into the national phase |
Ref country code: DE |
|
ENP | Entry into the national phase |
Ref document number: 2009255564 Country of ref document: AU Date of ref document: 20090227 Kind code of ref document: A |
|
WWE | Wipo information: entry into national phase |
Ref document number: 2009758811 Country of ref document: EP |
|
WWE | Wipo information: entry into national phase |
Ref document number: 6815/DELNP/2010 Country of ref document: IN |
|
WWE | Wipo information: entry into national phase |
Ref document number: 12919912 Country of ref document: US |