SCALABLE CONTINUOUS-WAVE ION LINAC PET RADIOISOTOPE SYSTEM
20200029420 ยท 2020-01-23
Assignee
Inventors
Cpc classification
H05H2007/082
ELECTRICITY
H05H7/04
ELECTRICITY
H05H7/00
ELECTRICITY
International classification
H05H7/00
ELECTRICITY
H05H7/04
ELECTRICITY
Abstract
A continuous wave ion linear accelerator PET radioisotope system is disclosed. The system includes a high brightness H.sup. ion source, a continuous wave RF quadrupole structure, and continuous wave RF interdigital structures to accelerate the ion beam to about 14 MeV. A high energy beam transport system is also described that includes a photo-detachment beam splitter and a magnet lattice for forming the proton beam into a beam having a Waterbag beam profile. The system also includes one or more targets upon which the proton beam is incident. The targets are either a high power metallic target oriented at about 10 degrees or a low thermal conductivity target oriented at about 35 degrees. The invention includes a method of producing PET isotopes by use of the systems described.
Claims
1. A continuous wave ion linear accelerator PET radioisotope system comprising: a high brightness H ion source that produces a multi-milliampere beam of H ions; a continuous wave radio frequency quadrupole structure that accelerates the multi-milliampere H ion beam to about 1 MeV; one or more continuous wave radio frequency interdigital structures that accelerate the multi-milliampere H ion beam to about 14 MeV; a high energy beam transport system that transforms the accelerated H ion beam to a uniform transverse profile proton beam; one or more high power target stations that include a target capsule upon which the uniform transverse profile proton beam is incident to produce PET radioisotopes; and a target capsule transfer system for recovery of the produced PET radioisotopes.
2. The system of claim 1, wherein the high energy beam transport system comprises one or more laser photo-detachment beam splitters that transform a portion of the accelerated H ion beam to a Gaussian profile proton beam.
3. The system of claim 2, wherein the high energy beam transport system further comprises one or more non-linear focusing magnet lattices that defocus the Gaussian profile proton beam into the uniform transverse proton beam profile.
4. The system of claim 1, wherein the uniform transverse profile proton beam is incident on the high power target station along an axis.
5. The system of claim 4, wherein the high power target station is windowless with axially symmetric cooling inlet and outlet connections, and having a cooling system working fluid of either water or eutectic gallium tin alloy, the target plate further comprising a face that includes a substrate upon which the uniform transverse profile proton beam axis is incident.
6. The system of claim 5, wherein the high power target station comprises a metallic target plate oriented at about a 10 degree glancing angle relative to the transverse uniform proton beam axis.
7. The system of claim 6, wherein the metallic target plate is made of copper and the substrate is yttrium.
8. The system of claim 6, wherein the metallic target plate is made of silver and the substrate is nickel.
9. The system of claim 5, wherein the high power target station comprises a low thermal conductivity target plate oriented at about a 35 degree glancing angle relative to the transverse uniform proton beam axis.
10. The system of claim 9, wherein the low thermal conductivity target plate is made of iridium and the substrate is tellurium oxide.
11. The system of claim 9, wherein the low thermal conductivity target plate is made of iridium and the substrate is copper selenide.
12. A method of producing PET radioisotopes comprising: introducing a multi-milliampere H ion beam into a continuous wave linear accelerator via a low energy beam transport to form a low emittance, multi-milliampere H ion beam; focusing the H ion beam via a continuous wave radio frequency quadrupole to accelerate the low-emittance, multi-milliampere H ion beam to about 1 MeV; accelerating the focused H ion beam to an energy of about 14 MeV; transporting the accelerated H ion beam to a high energy beam transport system via a beam pipe; transforming a portion of the accelerated H ion beam into a Gaussian profile proton beam; forming the Gaussian profile proton beam into a uniform transverse profile proton beam; transferring the uniform transverse profile beam to a target station that includes a target capsule, the target capsule contains a target plate that includes a substrate upon which the uniform transverse profile proton beam is incident, thereby producing one or more PET radioisotopes; cooling the target plate with a coolant working fluid of either eutectic gallium tin alloy or water; transferring one or more of the target capsules from the target station to one or more radiochemical processing hot cells; and opening the target capsule to remotely remove the target plate within the radiochemical processing hot cell to recover the produced PET radioisotopes.
13. The method of claim 12, wherein the PET radioisotope produced is Zirconium 89 (89Zr) and the target substrate is yttrium 89 (89Y).
14. The method of claim 12, wherein the PET radioisotope produced is Iodine 124 (124I) and the target substrate is tellurium 124 enriched oxide (124TeO2).
15. The method of claim 12, wherein the PET radioisotope produced is Bromine 76 (76Br) and the target substrate is selenium 76 enriched copper selenide (Cu276Se).
16. The method of claim 12, wherein the PET radioisotope produced is Copper 64 (64Cu) and the target substrate is nickel 64 (64Ni).
17. The system of claim 1, wherein the produced PET radioisotope is Zirconium 89 (89Zr).
Description
BRIEF DESCRIPTION OF THE DRAWINGS
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DETAILED DESCRIPTION
[0048] The following description is merely exemplary in nature and is not intended to limit the present disclosure, application, or uses. It should be understood that throughout the drawings, corresponding reference numerals indicate like or corresponding parts and features.
[0049] Before the present invention is described in further detail, it is to be understood that the invention is not limited to the particular embodiments described, and as such may, of course, vary. It is also to be understood that the terminology used herein is for the purpose of describing particular embodiments only, and is not intended to be limiting, since the scope of the present invention will be limited only by the appended claims.
[0050] A number of materials are identified as suitable for various aspects of the invention. These materials are to be treated as exemplary and are not intended to limit the scope of the claims. Although any methods and materials similar or equivalent to those described herein can also be used in the practice or testing of the present invention, a limited number of the exemplary methods and materials are described herein.
[0051] It must be noted that as used herein and in the appended claims, the singular forms a, an, and the include plural referents unless the context clearly dictates otherwise.
[0052] In general, the meaning of the various terms and abbreviations as used herein is as they are generally used and accepted in the art, unless otherwise specified. In order to aid in the understanding of the invention, specific meanings of several terms are provided.
[0053] As used herein, large scale production when applied to longer lived PET isotopes zirconium-89, iodine-124, and copper-64 means the provision of sufficient radioactivity to meet the demand of one million or more patient doses per annum.
[0054] The term high current as applied to beam current means a beam current of two milliamperes or greater. Similarly, the term multi-milliampere refers to currents of at least about two milliamperes. High power acceptance when applied to target stations requires managing the heat fluxes associated with high beam currents. The term high power is used to refer to power acceptance ranging from ten to many tens of kilowatts (kW).
[0055] Brightness applied to ion source output is a figure of merit defined as the number given by output beam current divided by the square of the beam emittance. Emittance means the two dimensional area in ion beam phase space that is enclosed by an equal intensity contour line enclosing 90% of the total beam current, normalized. The term high brightness as applied to ion source output means a brightness figure of three or greater.
[0056] As used herein, the term low emittance refers to a normalized total emittance of about 1.0 mm-mrad.
[0057] A continuous-wave (CW) linac refers to the continuous in time beam current pulse repetition rate for a 100% beam duty factor.
[0058] A beam having a Waterbag beam profile refers to a beam having a two-dimensional transverse beam profile with an rms uniformity of 5% or better.
[0059] Several types of beam transports are described and used herein. A low-energy beam transport (LEBT) permits high acceptance (95%) of the injected H.sup. beam at an ion energy of a few tens of keV. A medium-energy beam transport (MEBT) refers to beam having an ion energy of about 1 MeV. A modular high-energy beam transport (HEBT) refers to a transport at the final ion energy of about 14 MeV.
[0060] The term low thermal conductivity refers to a thermal conductivity of less than about 3 Wm.sup.1K.sup.1.
[0061] In general terms, the invention is a continuous wave ion linear accelerator PET radioisotope system that includes a high brightness H.sup. ion source that produces a multi-miliampere beam of H.sup. ions. A continuous wave radio frequency quadrupole structure accelerates the H.sup. ion beam to about 1 MeV. One or more continuous wave radio frequency interdigital structures further accelerate the beam to about 14 MeV. A high energy beam transport system transforms the accelerated beam to a uniform transverse profile proton beam. The uniform proton beam is incident on one or more high power target stations that include a target capsule where the PET radioisotopes are produced. The radioisotopes are recovered in a target capsule transfer system. The invention also includes a method of producing PET radioisotopes.
[0062] The high energy beam transport system includes one or more photo-detachment beam splitters that transform at least a portion of the accelerated H.sup. ion beam into a Gaussian profile proton beam. One or more non-linear focusing magnet lattices defocus the Gaussian profile proton beam.
[0063] The high power target station is windowless with axially symmetric cooling inlet and outlet connections. The cooling system working fluid is typically water or eutectic gallium tin alloy. The target station includes a face having a substrate upon which the proton beam is incident. When the target station includes a metallic target plate, the plate is oriented at a glancing angle of about 10 degrees relative to the proton beam. In several exemplary embodiments, when the target plate is copper, the substrate is yttrium; when the target plate is silver, the substrate is nickel.
[0064] As an alternative to the metallic target plate, the plate can be a low thermal conductivity plate, which would then be oriented at a glancing angle of about 35 degrees relative to the proton beam. In an exemplary embodiment, when the target plate is iridium, the substrate is tellurium oxide or copper selenide.
[0065] Examples of PET radioisotopes that can be produced by the system and method of the present invention include the following: Zirconium 89 (.sup.89Zr) when the target substrate is yttrium 89 (.sup.89Y); Iodine 124 (.sup.124I) when the target substrate is tellurium 124 enriched oxide (.sup.124TeO.sub.2); Bromine 76 (.sup.76Br) when the target substrate is selenium 76 enriched copper selenide (Cu.sub.276Se); and Copper 64 (.sup.64Cu) when the target substrate is nickel 64 (.sup.64Ni).
[0066] The present invention is a continuous-wave, fault-tolerant RF negative ion linac deployed in a scalable configuration with laser-photo-detachment beam splitter and non-linear focusing magnet arrangement with field strengths to provide for beam uniformization to the Waterbag beam profile. In this context, and as will be seen, in addition to utilitarian uniqueness which is expressed in this invention through the capability for economically advantageous scalability for large-scale production of PET radioisotopes previously envisioned as technically not achievable, by its high-energy CW ion linac and particle-beam-transport components which make up portions of the system of the invention, this special nature leads to a uniquely flexible, high-reliability configuration simultaneously accommodating multiple high-power acceptance target stations.
[0067] These characteristics provide the system with the ability to be: (a) rapidly and economically scalable for centralized supply of longer-lived PET radioisotopes for widespread availability to support translation of radio-immunoimaging protocols (immuno-PET) into the clinical standard of care; (b) highly reliable in CW ion linac operations due to modularity of design in RF power amplification which grants fault-tolerance, and allows faulty modules to be hot-swappable, further minimizing down-time; (c) capable of delivering high beam currents simultaneously to multiple target stations; (d) capable of uniformization of Gaussian beam to a Waterbag beam profile to maximize power acceptance; (e) capable of withstanding extreme thermal stress on target plates during irradiation; (f) able to minimize personnel exposure by highly reliable transfer of irradiated target plates to hot cells for radiochemical processing; and (g) adopted to the limitations of master/slave remote manipulators for isotope recovery in hot cells to meet As Low as Reasonably Achievable (ALARA) exposure guidelines for handling of radioactive materials. Some or all of these may be achieved through implementation of the present invention.
[0068] The radioisotope production components of the proposed system are arranged initially in a straight-linear fashion, progressing through the system from the low-energy end to the high-energy end. The components of the system of the invention include: (a) a DC volume-cusp ion injector source capable of high-brightness H ion beams; (b) a low-energy beam transport (LEBT) permitting high acceptance (95%) of the injected H beam; (c) a radio frequency quadrupole (RFQ) structure; (d) an RF coupler for medium-energy beam transport (MEBT); (e) a series of radio frequency interdigital (RFI) linac structures; (f) in an arc fashion, a modular high-energy beam transport (HEBT) incorporating a laser-photo-detachment (laser-wire) beam splitter and non-linear focusing magnet lattice; (g) a high-power acceptance, sandwich-type metallic target station; (h) a high-power acceptance, low thermal conductivity (e.g., oxides) target station; and (i) target capsule transfer components, terminating in the radioisotope processing hot cell with target capsule opening/closing device adapted for master/slave remote manipulation of the irradiated target plate.
[0069] To aid in appreciating certain technical background information, the contents of U.S. Pat. No. 6,777,893, which may be helpful in understanding the nature of the present invention, is hereby incorporated by reference into this disclosure.
[0070] The present invention utilizes an RFQ linac structure for high-current (10-200 mA) operations. RFQ structures have small ion beam diameters, and because the transverse focusing of the RFI linac structure is electric, similar to that of the RFQ structure, the RFI will have the same small diameter ion beam. Consequently, matching the ion beam from an RFQ into the RFI linac is straightforward. The RFI linac structure offers improved capabilities to capture and accelerate low-energy ion beams. With its improved beam quality and higher RF power efficiency for high-duty-cycle operations, such as continuous-wave (CW), the RFI linac can accelerate much higher currents than achievable with cyclotron technology.
[0071] The CW ion linac PET radioisotope system of the present invention provides acceleration to ion energies in the range of 10 MeV to 15 MeV of high-intensity CW negative ion beams, with beam currents on the order of 10 mA readily obtainable. By melding electric focusing-long recognized as the best method for focusing low-energy ion and proton beamsand acceleration of a high-current, CW, negative ion beam, this leads to an important advance in longer-lived PET radioisotope production. This performance advance enables the system of the present invention to provide the multi-milliampere proton beam currents for the irradiation of high-power acceptance targets that are essential for clinical translation of medical applications using longer-lived PET isotopes, such as immuno-PET with zirconium-89 and iodine-124.
[0072] The CW ion linac PET radioisotope system of the present invention combines a high-brightness negative ion (H.sup.) ion source with the strong RF focusing of the RFQ linac and the efficient acceleration of the RFI linac to provide compact, commercially-viable, linear acceleration of a multi-milliampere CW H beam at a relatively low cost.
[0073] The CW ion linac PET radioisotope system of the present invention includes modularity in the design of the CW ion linac and high-energy beam transport system (HEBT) for a highly reliable platform technology for medical isotope production. This design provides longer-lived PET radioisotopes requiring protons in the 0.1 to 0.2 times the velocity of light. With radioactive half-lives between 16 hours and 4.18 days, these longer-lived isotopes and their radiopharmaceuticals are suited to centralized production and distribution. The CW ion linac radioisotope system provides for high reliability in its operations by its modular, fault-tolerant RF power architecture, and its axially-symmetric target capsule, which eliminates the frequent failures associated with axial positioning systems in target capsule transfer.
[0074] The CW ion linac PET radioisotope system of the present invention may provide for the simultaneous irradiation of up to six high-power acceptance targets. This feature enables the scalability required for centralized supply of late-stage clinical trials involving large patient cohorts, as well as post-approval unit dose manufacturing for millions of PET scans annually. The modular HEBT system incorporates laser-photo-detachment beam splitters which preserve the parent H.sup. beam parameters, and dipole bending magnets to separate the parent H.sup. and proton beams for transport to the subsequent optical interaction cavity for the former, and a non-linear focusing magnet system for the latter.
[0075] The CW ion linac PET radioisotope system of the present invention may provide for the uniformization of the proton fluence rate incident on the target plate by incorporation of a non-linear magnet focusing system. The multiply-scattered, Gaussian beam profile undergoes flat-topping to the uniform Waterbag beam distribution for effective management of peak heat fluxes by the high-power acceptance target stations.
[0076] The CW ion linac PET radioisotope system of the present invention may also provide the high-power target station with the capability to manage extremely high heat fluxes (exceeding 1 kw/cm.sup.2). The use of eutectic GaSn alloy as the cooling system working fluid for the high-power metallic target plate results in linear heat removal all the way up to its boiling point of 1200 C., permitting multi-milliampere target currents and power acceptance in excess of 50 kW. This is achieved while operating far from the melting points of the target metals.
[0077] The CW ion linac PET radioisotope system of the present invention may provide high-power acceptance for the low thermal conductivity target station, with no beam window (windowless) to result in a multiply-scattered, Gaussian, beam profile requiring rastering of the beam by x-y steering magnets. Rather, high-power acceptance in excess of 10 kW is achieved through the non-linear focusing magnet system's flat-topped (Waterbag) beam profile which mitigates peak heat fluxes for the low thermal conductivity (3 Wm.sup.1K.sup.1) tellurium-124 enriched tellurium oxide. Tellurium oxide also possesses a relatively low melting point at 733 C., and the crystalline form used is brittle, cracking easily due to thermal stresses. Tellurium oxide is preferentially used for iodine-124 production due to the simplicity of thermo-chromatographic recovery.
[0078] The CW ion linac PET radioisotope system of the present invention may also provide axially-symmetric target capsules common to both the high-power metallic target and low thermal conductivity target. Axial symmetry (about beam axis 1B) of the coolant inlet and outlet channels obviates the need for an axial positioning system for such inlet and outlet. These axial positioning systems provide a frequent mode of failure in target capsule transfer systems.
[0079] The CW ion linac PET radioisotope system of the present invention includes targets that may be shielded in all directions. As is well known to those generally skilled in this art, it is important that an overall device like that which is disclosed herein be adequately shielded to prevent exposure to radiation with respect to people who work near and around such a system. In one implementation of the present invention, only the incoming beam pipe is a source of neutron leakage, so there is a substantial reduction in decommissioning costs and environmental impacts due to radio-activation of concrete and other nearby structural materials.
[0080] The CW ion linac PET radioisotope system is rapidly scalable, comprised of CW H.sup. linac, high-energy beam transport (HEBT)laser photo-detachment (aka laser wire) beam splitter, non-linear focusing magnetsfor up to six targets. For incident heat flux of up to 1 kW/cm.sup.2 on the target plate, we use eutectic GaSn alloy cooling with Ar gas overpressure (to prevent Ga oxidation). The extreme-power metallic target incorporates a unique high-power eight-sector collimator and elongated octagonal target plate into a titanium capsule (rabbit) for transfer to the target processing hot cell by pneumatic transfer system. The axially-symmetric rabbit needs no axial positioning, the most common failure mode of such systems. The target's large surface area, low critical angle, explosion welded yttrium cladding, and finned back offer the optimum combination for eutectic GaSn alloy coolant. It is believed that this is the first system to successfully use the Waterbag beam profile-since our HEBT uses octupole/dodecapole magnets for flat-topping the Gaussian beam.
[0081] As will be seen from the description of the invention set forth below, the system of the present invention directly and effectively addresses various performance, scalability, economic, and reliability issues.
[0082] As will be seen, the present invention offers a long-lived PET radioisotope production system which is rapidly scalable, highly reliable by its fault-tolerant modular design, and provides for economical, widespread availability of these isotopes.
[0083] The characteristics of the system of the present invention are directed to (a) the invention's proposed unique continuous-wave (CW) negative ion linear accelerator with optimal 14 MeV final energy; (b) the invention's fault-tolerant accelerator design, lending high reliability to its operation; (c) the invention's capability to accelerate multi-milliampere total beam currents to such optimal final energy; (d) such invention's unique HEBT design capability for simultaneous delivery of proton beam to up to six target stations, while it also preserves all desirable parent beam parameters using laser photo-detachment as the beam splitter mechanism; (e) such invention's unique uniformization of the transverse proton beam profile incident on the target plates; (f) such invention's two target capsule designs provide for uniquely high power acceptance for both iodine-124 and for zirconium-89 radioisotope production; and (g) such invention's target capsules incorporate axial symmetry of cooling channels, obviating the need for an axial positioning system, and affording high reliability in post-irradiation capsule transfer from target station to hot cell for radioisotope processing.
[0084] The two radioisotopes which are most commonly used in immuno-positron emission tomography, or immuno-PET, are iodine-124 and zirconium-89, with half-lives of 4.18 days and 3.27 days, respectively. A widely-recognized, longstanding technological barrier has precluded their reliable, economical, widespread availability. The present invention for a CW ion linac PET radioisotope system provides for their highly scalable, reliable, and economical supply.
[0085] Various objects, advantages and novel features, and further scope of applicability of the CW ion linac PET radioisotope system will be set forth in part in the detailed description to follow, taken in conjunction with the accompanying drawings, and in part will become apparent to those skilled in the art upon examination of the following, or may be learned by practice of the invention. Other objects and advantages of the invention may be realized and attained by means of the instrumentalities and combinations particularly pointed out in the appended claims.
[0086] The CW ion linac PET radioisotope system comprises a high-brightness DC volume-cusp H.sup. ion source as the injector for the LEBT, which focusing the H.sup. beam for acceleration by the RFQ. The RFQ structure has been proven capable of accelerating up to 30 mA of beam current at high-duty-factor. An RF coupler, or MEBT, between the RFQ and RFI accelerating structures performs matching of the beam ellipses. The RFQ and RFI linac tanks receive their RF power for acceleration of ions from modular RF amplifier (RFA) power blocks, which are fault-tolerant: each RFA power block can deliver its full rated power with up to 10% failed modules. The number of RFA power blocks may be increased to provide power for acceleration of still higher beam currents. The system, though initially configured to accelerate 6 mA of H.sup. beam, may be rapidly and economically scaled to accelerate 10 mA, or more, to the final energy of 14 MeV.
[0087] Modularity of design and fault-tolerance are highly-desired advantages in scaling production capacity to meet demand for production of medically urgent isotopes for cancer diagnosis and therapy. Scalability in isotope production capacity is further enabled by the modular nature of the HEBT portion of the system of the invention. Highly efficient beam splitting, while maintaining beam parameters that are key figures of merit for beam quality, i.e., size, divergence, energy, energy spread, and phase spread, is an important process which is incorporated in the HEBT design of the present invention. HEBT modules may be added to support up to six high-power target stations. Optimizing target yields for the long-lived PET radioisotopes identified as critical needs by the National Cancer Institute and IAEA is addressed in the present invention by the non-linear focusing magnet lattice and high-power target station portions of the system of the invention.
[0088] Turning attention now to the drawings, referencing first of all
[0089] Completing a description of what is shown in
[0090] Shown in
[0091] The full CW ion linac PET radioisotope system, as shown in
[0092] Shown in
[0093] Referring to
e+H.sub.2(v=0).fwdarw.H.sub.2(v>0)+e
H.sub.2(v>0)+e.fwdarw.H.sub.2.sup.(v>0).fwdarw.H.sup.+H
where v is the vibrational quantum number. Whereas the first reaction peaks for energetic electrons (100 eV), the yield of H.sup. in the second reaction of the process is maximized for lower energy, cold, electrons (1 eV). A bias voltage applied to the plasma lens 68 increases production of secondary electrons. This necessitates a magnetic filter to eliminate the energetic electrons from the cold region. In the extraction region, a permanent magnet filter in the extraction lens 69 removes any electrons from the beam before being brought to its final energy of 25-30 keV by the ground lens 70. The permanent magnet filter obviates the need for an electron trap in the LEBT 29 to prevent these electrons from being accelerated along with the H.sup. ion beam by the RFQ 30. The beam waist 71 is created in the vicinity of the ground lens 70. The vacuum box 72 incorporates a small x-y steering magnet to ensure the beam ellipse is properly centered for acceptance by the LEBT 29.
[0094] Shown in
TABLE-US-00001 TABLE 1 Accelerated Particle H- Resonant Frequency 200 MHz Ion Source Output Energy 27 keV RFQ Output Energy 1.0 MeV RFI Output Energy 14.0 MeV Beam Current 10.0 mA Beam Duty Factor 100% RFI Tanks 4 RFI Linac Length 5 m RF Cavity Power (Peak) 590 kW RF Beam Power (Peak) 140 kW RF Total Power (Peak) 720 kW RFQ Transmission Efficiency 95 % RFI Transmission Efficiency 100 % Total Length, Including Ion Source 8.26 m
[0095] In
[0096] Now referring to
[0097] Referring to
[0098] As an example it can be shown that this technique is effective for low energy (10-15 MeV) beams because the yield is inversely proportional to , the particle velocity in units of the velocity of light. Here, we have =0.17 for H.sup. ions at 14 Mev. The detachment cross-section is 3.510.sup.17 cm.sup.2 at 1.17 eV (1064 nm). In the H.sup. rest frame, the relativistic shifted, or Lorentz boosted, laser photon energy is E.sub.CM=E.sub.L [1 cos(.sub.L)], with and the Lorentz parameters of the H.sup. beam and .sub.L is the laboratory angle of the laser beam relative to the H.sup. beam. For a Gaussian laser beam with N.sub.L photons intercepting a Gaussian H.sup. beam of current I.sub.b at angle .sub.L, the yield Y.sub.1, the number of neutral hydrogen atoms produced per laser-H.sup. beam crossing, is given by the following approximation:
where .sub.b and .sub.L are the transverse rms sizes of the H.sup. and laser beams normal to the plane of incidence, and .sub.N(E.sub.CM) is the photo-detachment cross-section at photon energy ECM in the H.sup. rest frame. For illustration, in one embodiment using a 10 mA, 14 MeV H.sup. beam, N.sub.L=2.6810.sup.17, .sub.L=85, c=510.sup.9 cm/s, .sub.N (E.sub.CM)=3.510.sup.17 cm.sup.2, .sub.b=.sub.L=0.2 cm. Yield is enhanced above the fractional yield F.sub.1 of a single crossing by reflecting the laser beam through the H.sup. beam a number of times, N, to give the approximate fractional yield,
F.sub.N=1(1F.sub.1).sup.N
with Y.sub.1 at 1.510.sup.8 H.sup.0 atoms per 10 ns CW mode-locked laser 39 pulse, 0.5 mA, for N=8 mirror reflections, the total H.sup.0 current is 5 mA, effectively splitting the beam. The neutral H.sup.0 beam maintains nearly identical parameters as the parent H.sup. beam, including size, divergence, energy, energy spread, and phase spread.
[0099] The remaining electron is stripped by a long-lifetime hybrid boron-carbon (HBC) foil in foil holder 41 with an efficiency of nearly 100% given by the fractional yield as a function of H.sup.0 beam velocity in units of the speed of light, parametrized as follows:
[0100] where
[0101] a=0.4791018 cm.sup.2/.sup.2
[0102] b=0.00851018 cm.sup.2/.sup.2
[0103] c=0.1871018 cm.sup.2/.sup.2
[0104] d=foil density in atoms/g
[0105] t=foil thickness in g/cm.sup.2
[0106] =relativistic factor (0.17 at 14 MeV)
[0107] The remainder of the neutral beam (<100 W) is directed to a beam dump 42. As shown in
[0108] Referring to
[0109] In
[0110] Shown in
[0111] In
[0112] In
[0113] Next in
[0114] In
[0115] Multiphysics simulations can predict how target plate 60 performs under real-world conditions. Here, finite element analysis (FEA) utilized a 3D mesh for high-power metallic target plate 60 with 110.sup.6 nodes and 5.710.sup.6 elements. Eutectic GaSn coolant at 15 dm.sup.3 min.sup.1 across the back of the target plate 60 as shown in
[0116] Referring now to
[0117] Multiphysics simulations predict how target plate 63 performs under real-world conditions. Here, finite element analysis used a 3D mesh having 110.sup.6 nodes and 5.610.sup.6 elements for low thermal conductivity target plate 63. The back side of target plate 63 is cooled using 20 dm.sup.3 min.sup.1 of water at 20 C. inlet temperature. The pressure drop through the target capsule under these conditions is 3.5 bar. With inlet water pressure at 10 bar, a pressure drop of 3.5 bar, the pressure of the water behind the target plate 63 is 6.5 bar. The boiling point of water at this pressure is 162 C. Multiphysics simulations with 14 MeV proton beam at 1 mA beam current yield a maximum water temperature of 157 C. The maximum tellurium oxide temperature is 410 C., much less than the 550 C. limit, where the vapor pressure of the tellurium oxide is only 510.sup.4 mbar, ensuring enriched tellurium-124 losses are less than 0.1%. Cyclotron technology has not provided a low thermal conductivity target capable of more than 150 A with dual beam. The CW ion linac PET radioisotope system can deliver up to 6 mA total beam current to six low thermal conductivity target stations, a 20-fold increase in power acceptance.
[0118] Shown in
[0119] Next, in
[0120] Referring now to
[0121] In
[0122] Next,
[0123] Finally,
[0124] While the invention has been described in conjunction with specific exemplary implementations, it is evident to those skilled in the art that many alternatives, modifications, and variations will be apparent in light of the foregoing description. Accordingly, the invention is intended to embrace all such alternatives, modifications, and variations that fall within the scope and spirit of the appended claims.