WO2012095644A1 - Source de neutrons compacte à faible énergie - Google Patents

Source de neutrons compacte à faible énergie Download PDF

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Publication number
WO2012095644A1
WO2012095644A1 PCT/GB2012/050008 GB2012050008W WO2012095644A1 WO 2012095644 A1 WO2012095644 A1 WO 2012095644A1 GB 2012050008 W GB2012050008 W GB 2012050008W WO 2012095644 A1 WO2012095644 A1 WO 2012095644A1
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WIPO (PCT)
Prior art keywords
neutron
neutron source
source according
target
neutrons
Prior art date
Application number
PCT/GB2012/050008
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English (en)
Inventor
Paul Beasley
Oliver Heid
Timothy Hughes
Original Assignee
Siemens Aktiengesellschaft
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from GB201100442A external-priority patent/GB2487198A/en
Priority claimed from GB201104717A external-priority patent/GB2489400A/en
Priority claimed from GB1109558.5A external-priority patent/GB2491610A/en
Application filed by Siemens Aktiengesellschaft filed Critical Siemens Aktiengesellschaft
Publication of WO2012095644A1 publication Critical patent/WO2012095644A1/fr

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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
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
    • G21G1/06—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation
    • 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
    • H05H5/00—Direct voltage accelerators; Accelerators using single pulses
    • H05H5/04—Direct voltage accelerators; Accelerators using single pulses energised by electrostatic generators
    • H05H5/045—High voltage cascades, e.g. Greinacher cascade
    • 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
    • H05H5/00—Direct voltage accelerators; Accelerators using single pulses
    • H05H5/06—Multistage accelerators
    • H05H5/066—Onion-like structures
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/001—Recovery of specific isotopes from irradiated targets
    • G21G2001/0036—Molybdenum

Definitions

  • the present invention relates to neutron sources, and in particular provides a compact, low energy neutron source which can be used in a number of applications.
  • Neutron sources are known and find use in diverse applications, such as fault detection in turbine blades, cancer treatment, production of Molybdenum-99 (Mo-99) isotope for use in nuclear medicine, and for security inspection.
  • Mo-99 Molybdenum-99
  • Cf-252 Californium-252
  • US2009/0225922 An example is described in US2009/0225922.
  • Neutron tubes are known. These have a limited lifetime unless they are continually refilled. They contain tritium ( 3 H) which restricts general application. Such sources have been used for down-hole well logging (e.g. US7139349, US6922455) .
  • Nuclear reactors can generate large numbers of free neutrons with a wide range of energies. For applications requiring low-energy neutrons, the neutrons from the reactor would need to be moderated. Such facilities are large. They are not portable and their range of applications is restricted by the size of the necessary installation. Only a small number of suitable reactors are available in the world, and have lengthy maintenance schedules. Safety concerns limit their wider application.
  • Neutron sources based on particle accelerators have conventionally been least favoured, for example because of their cost and complexity, for example their requirement for long radio frequency quadrupoles (e.g. US2006/0140326) .
  • the present invention provides a small and compact, energy efficient neutron source providing neutrons of relatively low energy in an energy efficient manner.
  • Fig. 1 schematically illustrates a DC accelerator useful in a method according to a first embodiment of the invention
  • Fig. 2 schematically illustrates apparatus for producing a neutron flux according to the first embodiment of the present invention
  • Fig. 3 schematically illustrates a tandem DC accelerator useful in a method according to a second embodiment of the invention
  • Fig. 4 schematically illustrates apparatus for producing a neutron flux according to the second embodiment of the present invention
  • Fig. 5 schematically illustrates the known interaction between boron atoms and thermal neutrons in BNC .
  • the present invention provides methods and apparatus for producing a neutron flux using an electrostatic accelerator.
  • the present invention provides a neutron source comprising a compact electrostatic particle accelerator with one or more suitable targets. Charged particles are accelerated towards a target by the particle accelerator. Once a charged particle hits a target, a different type of particle is released. In some embodiments, a single target is provided. Charged particles hit the single target and release neutrons. In other embodiments, more than one target is provided, in "tandem". Accelerated charged particles hit a first target, and release a different type of charged particle. An example of such action is the stripping of electrons from H ⁇ ions:
  • the electrostatic accelerator comprises concentric shells each divided into two parts at an "equatorial" plane. Such parts may be halves, but need not be exactly equal. However, they will be referred to within the present description as “halves” for ease of reading.
  • the concentric shells perform as capacitors in a Cockcroft-Walton (or Greinacher) cascade.
  • Greinacher Greinacher
  • the electrostatic accelerator is preferably operated in a high vacuum, enabling higher electric fields to be generated than would be the case with pressurised gas insulation between the shells, for example in excess of lOMVm -1 .
  • a series of aligned holes through the shell halves serves as a beam tube.
  • An example of such an electrostatic accelerator is illustrated in Fig. 1, where concentric shells 102 are divided 103 at an equatorial plane, while a series of aligned holes 104 allows an incoming particle beam 105 to reach a target 100 within a central region 101, within an innermost shell .
  • Each shell is charged to a high voltage as compared to its outwardly neighbouring shell.
  • Fig. 2 shows a further development of this idea, in a so-called tandem electrostatic accelerator.
  • an electric field is generated which attracts first particles 105 of a first polarity, as described with reference to Fig. 1.
  • Such first particles are accelerated through the concentric shell structure until they reach the central region 101 within the innermost shell. There, they hit a particle converter target 200 and release a beam 205 of second charged particles of a second polarity, opposite to the first polarity.
  • Such second charged particles are repelled out of the accelerator through a second series of aligned holes 204 in the concentric shells by a voltage gradient of opposite polarity to that which accelerated the first particles into the accelerator.
  • the second particles reach a second target 210.
  • Each shell is charged to a high voltage as compared to its outwardly neighbouring shell.
  • such concentric-shell electrostatic accelerators form a component of compact, low- energy neutron sources.
  • Fig. 3 shows a neutron source according to a first embodiment of the invention.
  • Protons (H + ions) 22 may be accelerated from a source 12 to the centre of the accelerator 10 where they hit a neutron generator target 14, such as a proton spallation target, for example, lithium, beryllium or carbon.
  • a lithium Li-7 target produces neutrons 16 from the (p,n) reaction Li-7 (p, n) Be-8.
  • the resultant neutron flux 16 is unaffected by the electrostatic field, and exits the accelerator for use as required .
  • Such a system is compact enough to allow mobile deployment or relatively easy incorporation into existing sites.
  • Fig. 4 schematically illustrates a second embodiment of the present invention, in which a tandem accelerator 30, such as shown in Fig. 2, is employed. Rather than placing a neutron- source target 14 in the centre of the accelerator, as in the example of Fig. 3, a particle converter target 34 is placed in that position. First charged particles 36 are provided by a source 32 and are directed towards the particle converter 34.
  • the first charged particles 36 interact with the particle converter 34, and produce second charged particles 38, of polarity opposite to that of the first charged particles 36 and travelling in the same trajectory as the first charged particles.
  • the second charged particles will be accelerated out of the accelerator 30, while the original particles are accelerated into the accelerator along path 204 (Fig. 2) .
  • H ⁇ ions 36 may hit a particle converter 34, being an ion stripper arrangement and conventional in itself, and be converted to H + ions, protons 38.
  • the accelerator 30 would need to be charged to a positive voltage to ensure that H ⁇ ions 36 are accelerated towards the particle converter 34, and H + ions, protons 38, are accelerated away from it.
  • a target 40 is positioned outside of the accelerator.
  • the second charged particles 38 leave the accelerator and hit target 40.
  • the beam of second charged particles 38 hits target 40 and causes emission of other particles 42.
  • the other particles 42 are neutrons .
  • the present invention may accordingly be applied both to linear accelerators and tandem accelerators.
  • Various different targets may be used, as will be described in more detail in the following examples.
  • a neutron flux may be produced using a compact linear neutron generator.
  • a conventional linear DC electrostatic accelerator 10 similar to that described with reference to Fig. 1, is provided with a beam 22 of protons (H + ions) from a proton source 12.
  • a target of neutron source material 14 such as a thin Lithium Li-7 target, which produces neutrons 16 from the (p,n) reaction Li-7 (p, n) Be-8 or similar .
  • the Li-7 reaction is particularly advantageous because it is a transition reaction which, at around 1.885MeV, produces a collimated neutron beam 16.
  • the collimated neutron beam 16 can be directed at a moderator 18 to produce an epithermal neutron spectrum.
  • An epithermal neutron is a neutron that has energy greater than that of a thermal neutron, but not as large as for fast neutrons, so having a modest requirement for shielding.
  • epithermal neutrons of about 2.3MeV may be generated directly.
  • the epithermal neutrons, generated directly or emerging from moderator 18 may then be employed as required.
  • the protons H + ions
  • the protons are accelerated to the centre of the accelerator 10, at which point they cross the centre into the shell structure of the accelerator on the opposite side, which has a decelerating field.
  • the incident proton beam 22 loses a portion of its energy as it passes through neutron-source material 14. This resulting proton beam 24 exits the target, and is gradually slowed as it passes through the accelerator 10 and is collected in the structure of the DC electrostatic accelerator, acting as a collector assembly. In this way, the energy of the beam is recovered, as may be understood from conservation of energy.
  • the incident proton beam accelerates as it gains energy from the electrostatic field. Energy is continually supplied from a power supply unit to maintain the accelerating electric field. As the same charged particle beam exits the accelerator, the beam sees a decelerating field and the protons slow down giving energy back to the accelerator.
  • the proton source 12 is replaced with a source of deuterium ions 2 H + (D + ) .
  • the neutrons are generated as a result of accelerated particles of deuterium 2 H + (D + ) hitting a target 14 of beryllium Be-10 in a Be-10 (d, n) C-ll reaction to produce carbon-11 and a free neutron.
  • neutrons may be generated as a result of accelerated particles of deuterium 2 H + (D + ) hitting a target 14 of beryllium Be-9 in a Be-9 (d, n) C-10 reaction to produce carbon-10 and a free neutron
  • the free neutron may then be employed as required.
  • a tandem DC electrostatic compact accelerator 30 similar to that described with reference to Fig. 2, is provided with a source 32 of H ⁇ ions, and produces a beam 36 of H ⁇ ions directed towards the centre of the accelerator 30.
  • an ion stripper arrangement 34 such as a carbon stripper foil which is conventional in itself
  • the resulting H + beam 38 is incident upon a target material 40 which produces a neutron flux 42 in reaction to the incident protons.
  • the material 40 may be a proton spallation target such as Li, Be, C.
  • the Li-7 (p, n) Be-7 reaction which takes place if a lithium target is used is particularly advantageous because it is a transition reaction which, at around 1.885MeV, produces a collimated neutron beam 42.
  • Other materials may produce similar results.
  • the collimated neutron beam 42 may be directed at an optional moderator 44, which could be a simple water vessel or wax block, to produce a neutron spectrum of appropriate energy profile.
  • the resultant neutron flux may be employed as required.
  • the neutron sources of the present invention as described above and defined in the appended claims, have the advantages of being compact with a small footprint and requiring modest amount of power, mainly for the ion source and vacuum pumps.
  • the apparatus would also have a very simple user friendly interface for non-expert operation.
  • the system could be made portable using a simple electrical generator.
  • the compact low-energy neutron source of the present invention may find many applications, and the following description will give some examples of practical uses for the neutron sources of the present invention.
  • the neutron sources of the present invention may be employed in various processes and applications for scanning materials for explosives and nuclear materials as described for example in patent publications US2009/0225922A1, US2009/0114834A1, US2009/0271068A1, US2007 / 0295911A1 , US5278418, US5124554.
  • the present invention provides a compact particle accelerator for use in the generation of neutrons, suitable for use in security inspection.
  • security inspection which may benefit from the present invention include: for luggage, cargo containers, vehicles, mine detection.
  • a security inspection system with a small footprint would enable the detection of explosive and fissile materials.
  • low-energy neutrons with energy ranging from Thermal-8MeV are required.
  • Such neutron beams may be generated by the neutron source of the present invention, for example by a lOMeV ⁇ mA proton or deuterium beam accelerated into a neutron generator material such as Li, Be, C etc.
  • the proton spallation generates a high flux of neutrons in this energy spectrum.
  • Such a system would have the benefit of possible mobile deployment, or relatively easy incorporation into existing sites.
  • BNCT Boron Neutron Capture Therapy
  • a cancerous cell 50 is seeded with a compound containing boron- 10 52.
  • An incident neutron 54 interacts with a boron-10 nucleus to form an unstable boron-11 nucleus 56.
  • the combined range of the lithium-7 nucleus 57 and the alpha particle 58 is understood to be in the range of 8-9 microns, while the typical cell diameter is about 10 microns. This means that radiation damage is confined mostly within the target cell.
  • the methods and apparatus of present invention allow production of a neutron flux for use in BNCT, without the need for a large facility or use of a nuclear reactor.
  • BNCT a neutron flux of about 109 epithermal neutrons/cm 2 /s is required in order to keep the treatment time to 30 minutes, which is regarded as a maximum acceptable treatment time due to considerations of patient comfort and patient throughput.
  • epithermal energies are best suited for this treatment as these then thermalise in tissue. If thermal neutrons are used, the tumour has to be exposed as thermal neutrons do not penetrate far enough into the body but get stopped. Epithermal neutrons enter the body and are slowed down after a few centimetres, allowing them to reach a patient's tumour without having to surgically expose the tumour.
  • epithermal neutrons The element most often studied to produce these epithermal neutrons is lithium, which has a resonance for neutron production between 2.3 - 2.5 MeV, just above 1.88 MeV, the threshold proton energy at which neutrons begin to be produced from this target.
  • epithermal neutrons are generated directly before being used to treat the patient.
  • a compact DC electrostatic accelerator is configured with an voltage just above the threshold for boron neutron capture with an H+ ion source.
  • H + ions are accelerated to -2.3MeV to the centre of the accelerator where they hit a lithium neutron generator target.
  • the subsequent collimated epithermal neutrons, unaffected by the electrostatic field exit the accelerator and enter a patient undergoing BNCT.
  • Nuclear Medicine is currently used in the diagnosis of tumours, and investigations into other medical conditions .
  • Technetium Tc-99 m is an important radioisotope used in Nuclear Medicine. Currently, it is produced in a two-part process. The first part of the process involves the production of Molybdenum Mo-99. The Mo-99 produced then decays to Tc-99 m with a half life of 66 hours.
  • the Mo-99 is produced in a high flux nuclear reactor using HEU (highly enriched Uranium) .
  • HEU highly enriched Uranium
  • a Tc-99 m generator is a device used to extract the metastable isotope Tc-99 m of technetium from a source of decaying molybdenum Mo-99 at the point of use.
  • Mo-99 has a half-life of 66 hours and can be easily transported over long distances to hospitals, whereas its decay product technetium Tc-99 m is extracted and used for a variety of nuclear medicine diagnostic procedures.
  • Technetium Tc-99 m has a half-life of only 6 hours, which is inconvenient for transport, but is useful in medical diagnostic procedures.
  • Conventional Mo-99 / Tc-99 m generators use column chromatography, in which Mo-99 in the form of molybdate, Mo0 4 2 ⁇ is adsorbed onto acid alumina (AI 2 O 3 ) . When the Mo-99 decays, it forms pertechnetate Tc0 4 ⁇ , which because of its single charge is less tightly bound to the alumina.
  • the solution of sodium pertechnetate may then be added in an appropriate concentration to a pharmaceutical to be used, or sodium pertechnetate can be used directly without pharmaceutical tagging for specific procedures requiring only the Tc-99 m 0 4 ⁇ as the primary radiopharmaceutical.
  • Tc-99 m generated by a Mo-99/Tc-99 m generator is produced in the first 3 parent half lives, or approximately one week.
  • clinical nuclear medicine units purchase at least one such generator per week, or order several in a staggered fashion.
  • Mo-99 is currently the most commonly used radioisotope in nuclear medicine, but in the future there may be other radioisotopes which may be prepared using the neutron source of the present invention, and may be found useful for SPECT (single-photon emission computed tomography) and/or PET (positron emission tomography) systems. The latter currently focus on proton reactions from cyclotrons because compact neutron sources are less common.
  • the neutron generation sources and methods of the present invention enable alternative methods and apparatus for producing radioisotopes such as Mo- 99.
  • Mo-99 finds utility both as a product in itself, and as an intermediate product in a method of producing Tc-99 m , which methods and apparatus do not require the use of a high flux nuclear reactor and HEU.
  • Mo-99 may be produced using a compact neutron generator through a Mo-98 (n, ⁇ ) Mo-99 route.
  • a neutron beam may be produced and directed towards moderator 18. After the moderator 18, the neutrons hit a target 20 including Mo-98. This interaction results in the production of Mo-99 through an Mo-98 (n, ⁇ ) Mo-99 reaction.
  • the neutron beam may be produced as described above, either by a proton beam acting upon a lithium target, or deuterium ions 2 H + (D + ) hitting a target 14 of beryllium Be-10 in a Be- 10(d,n)C-ll reaction to produce carbon-11 and a free neutron.
  • the free neutron may then be directed towards the Mo-98 target 20 to produce Mo-99 in an Mo-98 (n, ⁇ ) Mo-99 reaction.
  • Mo-99 may be produced through a U-235 fission route with an energy recycling proton beam.
  • a material 14 which produces neutron beams 16 in response to an incident proton or deuterium ion beam 22.
  • the resultant collimated neutron beam 16 is directed at a moderator 18, which produces an epithermal neutron spectrum.
  • the neutrons hit a subcritical Uranium U-235 target to produce U-236 through the U- 235 (n, ⁇ ) U-236 reaction.
  • Mo-99 may then be separated from other fission products in a hot cell.
  • the resulting Mo-99 is removed from the U-235 target by a chemical process which is conventional in itself.
  • Fig. 4 schematically represents an example of apparatus according to second embodiment of the present invention, using a tandem DC electrostatic accelerator.
  • Collimated neutron beam 42 is directed at a moderator (not shown in the drawing, but could be a simple water vessel or wax block) to produce an epithermal neutron spectrum. After the moderator, the neutrons hit a Mo-98 target 44, producing Mo-99 through the Mo-98 (n, ⁇ ) Mo-99 reaction. In a second example of generating Mo-99 using a tandem compact neutron generator as shown in Fig. 4, Mo-99 is produced through the U-235 fission route.
  • an ion stripper arrangement 34 which produces a proton beam 38 in response to the incident H- ions 36.
  • the proton beam is directed to target 40, which produces neutron beams 42 in reaction to the incident protons.
  • the target 40 may be of Li-7 as described above.
  • the neutrons hit a subcritical Uranium U-235 target 44 to produce U-236 through the U-235 (n, ⁇ ) U-236 reaction.
  • the U-236 fissions to become Mo-99 plus other fission products and neutrons.
  • Mo-99 may then be separated from other fission products in a hot cell.
  • the resulting Mo-99 is removed from the U-235 by a chemical process which is conventional in itself .
  • the neutron beam generating apparatus and methods of the present invention allow simplified on-site production of Molybdenum Mo-99 without the use of large and unwieldy, or hazardous, apparatus.
  • Mo-99 is of use, for example, in the preparation of Technetium Tc-99m for use in Nuclear Medicine.
  • neutron beams are produced in-situ from readily generated H + , 2 H + or H ⁇ ion beams. This avoids the conventional requirement for a neutron source, which is usually a large piece of equipment, a particle accelerator or a reactor.
  • Fig. 6 shows an electrical schematic diagram of a Cockcroft- Walton (or Greinacher) cascade.
  • the capacitors 61 are formed by the concentric shells, and diodes 62 are used to join the shells together in an appropriate manner to form a Cockcroft-Walton (or Greinacher) cascade.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • General Engineering & Computer Science (AREA)
  • Particle Accelerators (AREA)

Abstract

La présente invention concerne une source de neutrons qui comprend un accélérateur de particules électrostatique (10; 30) et un matériau cible émetteur de neutrons (14; 40) agencé de sorte que des particules chargées (22; 36) puissent être accélérées par l'accélérateur de particules électrostatique pour frapper le matériau cible émetteur de neutrons, libérant des neutrons (16; 42). L'accélérateur de particules électrostatique comprend des enveloppes concentriques (102), chacune divisée en deux parties au niveau d'un plan équatorial (103), et comprend en outre des diodes connectées à des parties d'enveloppe à travers le plan équatorial.
PCT/GB2012/050008 2011-01-12 2012-01-05 Source de neutrons compacte à faible énergie WO2012095644A1 (fr)

Applications Claiming Priority (6)

Application Number Priority Date Filing Date Title
GB1100442.1 2011-01-12
GB201100442A GB2487198A (en) 2011-01-12 2011-01-12 Apparatus and methods for the production of mo-99 using a compact neutron generator
GB1104717.2 2011-03-21
GB201104717A GB2489400A (en) 2011-03-21 2011-03-21 A compact epithermal neutron generator
GB1109558.5 2011-06-08
GB1109558.5A GB2491610A (en) 2011-06-08 2011-06-08 A compact neutron generator for performing security inspections

Publications (1)

Publication Number Publication Date
WO2012095644A1 true WO2012095644A1 (fr) 2012-07-19

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20170041215A (ko) * 2014-08-06 2017-04-14 리써치 트라이앵글 인스티튜트 고효율 중성자 포획 생성물의 제조
WO2018048906A1 (fr) * 2016-09-06 2018-03-15 Bnnt, Llc Sources de lumière à rayonnement de transition
JP2021530689A (ja) * 2018-07-09 2021-11-11 アドバンスド アクセレレーター アプリケーションズ 中性子アクティベータ、当該中性子アクティベータを含む中性子放射化システム、および当該中性子アクティベータが実行する中性子放射化方法

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