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Introduction Measuring the beam profile on a medical cyclo-tron in real time can aid in improved tuning of the cyclotron and give important information for a smooth operation. Typically the beam profile is measured by an autoradiography technique or even by a scintillator that can be viewed in real time [1, 2]. Another method is to use collimators in front of the target to assess the beam center-ing [3]. All these methods have potential draw-backs including; an inability to monitor the beam in real time for the radiograph, exhibiting a non-linear correlation in signal response to the power deposited for a scintillator, and not providing a 2-dimensional profile of the complete beam for collimators. Our goal was to design a realtime, linear, 2-dimensional beam-profile monitor that is able to withstand the high power of a PET cyclotron. Material and Methods The beam-profile monitor (PM) is designed for the TR13, a 13MeV negative hydrogen-ion cyclotron at TRIUMF. The design follows the concept of a ‘harp’ monitor, widely used at TRIUMF for tuning proton and radioactive ion beams, and is installed on the extraction port without separation from the tank vacuum. The TR13 monitor is designed to withstand a 13 MeV proton beam with a beam current of up to 25 µA, has an active area of 10 by 10 mm and does not affect the 10-7 torr tank vacuum. The device consists of a water-cooled Faraday cup made out of aluminium for low activation and two orthogonal rows of eight tungsten electrodes each mounted on a water-cooled support frame. Electrodes are spaced 1 mm apart from each other, see FIG. 1. The electrodes are electrically isolated from each other and each has a current pickup soldered to it. The material and the shape of the electrodes are optimized to withstand the deposited power of the proton beam. A voltage of -90 V is applied to the electrodes to repel secondary electrons and prevent crosstalk between neighbouring electrodes. The electrode current is amplified using a custom current amplifier, and read by an ADC. From there, the current data is displayed on a PC. This allows one to observe changes of the beam profile in real time. The electronics are designed to read out all sixteen channels in parallel, or, if only a limited number of ADC channels are available, to cycle through the different channels. In our current setup all sixteen channels are read out simultaneously. Results and Conclusion The beam-profile monitor provides a real-time representation of the proton beam, see FIG. 2. The data can also be recorded and analyzed at a later time. The linearity of the monitor has been measured up to 30 µA of proton beam current [4]. With the use of the monitor, it was possible to increase the output of the ion source into the target by 50% in comparison to the standard tune.

Introduction The increasing demand for [18F]FDG for clinical PET-CT and the efficiencies associated with large production runs have encouraged endeavors to increase the amount of 18F− produced by cyclotrons in a single run. The amount of 18F− is determined by the saturation yield of the nuclear reaction, the irradiation time and the beam current striking the target. The saturation yield is a function of beam energy (typically fixed for PET cyclotrons), the enrichment of the H218O (typically > 97 %) and the efficiency of the target design. Target design has already been optimized on current systems. Diminishing gains in activity are achieved by extending the irradiation time much beyond 3 hrs, so the main focus has been to increase beam current onto the targets. Increasing the beam current requires: i) a cyclotron capable of producing the increased beam current; ii) targets that tolerate the beam current without appreciable loss in saturation yield; iii) sufficient shielding of the cyclotron and hot cells to accommodate the proportionally larger radiation dose rates during higher current irradiation and from the larger activities delivered to the hot cells. We reported [1] that the self-shielded targets fitted to our cyclotron can accommodate 100 µA currents without appreciable loss in saturation yield. We also identified the potential of routine production at 200 A (100 A per target in dual target irradiation mode), but had not establish its long-term viability in routine use. We present our experience in using 200 µA for routine production of 18F- since September 2012. Material and Methods Our PETtrace cyclotron was installed in 2002 and has been used for routine production of various 18F and 11C tracers since January 2003. It has been upgraded incrementally so that it is now equivalent to a current generation PETtrace 880 cyclotron, which is specified at a total beam current of 130 µA. The only components on our cyclotron currently not part of the standard PETtrace 880 cyclotron configuration are the self-shielded targets and a license which allows total target beam current of 200 µA. The self-shielded targets utilize a W/Cu alloy for the main body of the target surrounding the Havar foil to provide shielding from the Havar foil by a factor of about 10 and shielding of any remnant 18F- activity in the targets by a factor of about 100 [1]. The niobium target chamber is the same size as used in the standard GE Nb25 targets. However, it dispenses with the He cooling and the vacuum foil. Only the water foil is used, which is directly exposed to the vacuum in the chamber. Foil cooling is through the water in the target chamber. One of the issues that we previously identified [1] is beam stripping by gas molecules in the vacuum tank. The amount of beam that is stripped and which impacts on components in the cyclotron is proportional to the beam current. At high currents, this can result in a runaway condition, where the effects of the stripped beam deteriorate vacuum; this then results in more beam stripping and more severe effects. The effect of diffusion pump maintenance on vacuum system performance and on the reduction of beam stripping was investigated as part of this study. We have previously found that running the ion source gas at a low flow rate (2 sccm) when cyclotron is not used greatly reduces deterioration of ion source performance over time and with use [1]. This gas flow also appears to have a beneficial effect on the vacuum. Ion source gas flow when cyclotron is off has been employed throughout the evaluation period. [18F]FDG was produced with TRACERlab MXFDG modules or FASTlab modules using both Phosphate and Citrate cassettes. Stability studies of [18F]FDG were performed to ensure it met specifications over the specified expiry time. Our current stabilization regime did not have to be adjusted for the higher activities produced with the higher beam currents. [18F]FDG yields were calculated using input activity estimates from saturation yield and beam time and current and the non-decay corrected [18F]FDG activity measured at the end of synthesis. Thus yield calculations include target yield variations and losses in the transfer lines and not just synthesis yield. Results and Conclusion The flip-in probe to extraction foil transmissions as a function of ion source gas flow are given in TABLE 1. Transmission decreases with increasing ion source gas flow, as expected for a system with an internal ion source. In addition, diffusion pump maintenance had a positive impact on the transmission and this is of particular benefit at the higher beam currents where minimising beam stripping becomes more critical. The ion source output, however, decreases with decreasing ion source gas flow; hence ion source gas flow is a compromise between ion source output and probe to foil transmission. We currently use a gas flow of 5.5 sccm for our 200 µA runs. Over the period from 1st September 2012 to end of March 2014, a total of 419 [18F]FDG produc-tions were performed at total target beam currents ranging from 160 µA to 200 µA, with 227 production runs being performed at 200 µA. Beam times were typically 90 to 120 min, with some productions up to 180 min. The [18F]FDG yields are summarized in TABLE 2. The yields for the FASTlab phosphate and citrate cassettes have been listed separately in TABLE 2 as they are known to be different [2,3]. The yields obtained with the TRACERlab MXFDG are also shown. The yields at 200 µA total target current are not appreciably different from those at < 200 µA current, irrespective of the synthesis method. Consistency of yield is also not adversely impacted by the higher beam current. For a 180 min, 200 µA test production, the [18F]FDG activity produced using the FASTlab phosphate cassette was 763 GBq (20.6 Ci). Clinical productions with the FASTlab phosphate were limited to 130 min maximum beam time for 200 µA and achieved a maximum [18F]FDG activity of 656 GBq (17.7 Ci). The tolerance to a reduction in performance of the critical components to achieve high current operation (RF, ion source output and vacuum system) is reduced at high beam currents. The requirements for routine maintenance of ion source, targets and extraction system, however, have not increased with the increase in beam current from 160 µA to 200 µA. Extraction foil life and ion source maintenance intervals have remained at about 2000 Ah and >120 µAh, respectively. As more experience has been gained with the self-shielded targets, service interval is actually being extended from about 10,000 µAh to 20,000 µAh, despite the higher beam currents. Diffusion pump maintenance is currently recommended every 5 years, but a 2 year maintenance interval may be advantageous for 200 µA, given the observed deterioration over a 5 year period and the improvement in performance post service (Table 1). The more frequent service is associated with the additional costs of diffusion pump oil and an extra day of scheduled down-time. Typically, vacuum is sufficiently well established 24 h after opening of the vacuum tank to run 200 µA beams with the vacuum and beam conditioning that we employ. The targets generally have coped well with the 100 µA per target current (200 µA total beam current for dual target irradiation) over this 18 month period. However, currents of 80 µA to µ100 A per target in dual target irradiation mode reduce the tolerance to sudden increases in one of the target currents. There were 4 occasions (2 test beams and 2 production beams) when there were sudden increases of target current from 90 µA and 100 µA to about 150 µA. The rapid increase in heat deposited on the foil and target chamber and the resultant rapid pressure rise in the target chamber could not be withstood by the foil and target foil rupture ensued. This compared to 1 target foil issue over a similar period of time (18 months) at lower beam currents on the standard Nb25 target. Three separate causes were identified for these overshoots in target current: 1) behavior of control system when beam is allowed to continue past the set time; 2) large changes of set current of one of the two targets irradiated during a dual irradiation test beam and 3) an issue with DEE voltage regulation caused by the mechanical flap controls. These issues have been addressed by procedural changes (issues 1 and 2) and by fitting an available upgrade of the mechanical flap control mechanism (issue 3). The two target foil ruptures during production did not cause cancellation or delays to patient scanning, as the demand could be met by multi-ple productions and deliveries from the unaf-fected target. No unscheduled down-days occurred during the evaluation period. We have been able to achieve routine operation at 200 µA beam current through careful optimization of the critical components and parameters and a maintenance regime that we have detailed previously [1]. This maintenance scheme has not changed for the routine 200 µA operation. The safety margin, however, is reduced and so careful monitoring of the system is required to ensure that issues in one of the subsystems do not cause major events such as target foil ruptures. Our [18F]FDG yields have been maintained at the higher current and 200 µA allows large quantities of [18F]FDG to be produced routinely in a single run with relatively short beam times.

Introduction Temperature modeling using Finite Element Analysis (FEA) is widely used by particle beam-line designers as a useful tool to determine the thermal performance of an irradiated target system. A comparison study was performed between FEA calculated temperatures on platinum with experimental results using direct thermocouple measurements. The aims are to determine the best beam model for future solid target design, determine the maximum target current for different target materials and the temperature tolerance for any modification to our existing solid targetry system. Material and Methods The theoretical temperature of the target sys-tem was determined using SolidWorks 2013 with Flow Simulation Analysis (FSA) module. The FSA module determines the maximum temperature inside the target material given the global conditions (material specification, flow rates, boundary conditions, etc.) for a given target current. The proton beam was modeled as a volumetric heat source inside the target material based on the distribution of energy loss in the material along the beam axis. The method used by Comor, et al1 was used in this study. The method segmented the target material into five individual layers, each layer being 50 m thick. The energy lost per layer was calculated using SRIM3 and converted into the power lost per layer. A thickness of 250 μm of platinum completely stops the impinging proton beam at 11.5 MeV with the highest deposition of power per layer corresponding to the Bragg peak. The target material used in the simulation reflects the physical target disk used for temperature measurements (platinum, dia. 25.0 mm, thickness 2.0 mm) with two K-type thermocouples (dia. 0.5 mm, stainless steel sheath) embedded in the platinum disk. One thermocouple is located in the geometric center, while the other is located at a radial position 8 mm from center. The outer thermocouple is to determine the peripheral temperature near the o-ring seal. Temperature was maintained below the melting point for the material (Viton®, melting point 220 °C) during the irradiation to ensure the integrity of the water cooling system. The solid targetry system used in this study is an in-house built, significantly modified version2 of a published design1. The solid target system is mounted onto an 18/18MeV IBA Cyclotron with dual ion source, on a 300mm beam-line with no internal optics or steering magnets. A graphite collimator reduces the beam to 10mm in diameter and a degrader is used to reduce the proton beam energy to 11.5 MeV, considered suitable for production of radiometal PET isotopes 89Zr and 64Cu. Temperature was measured with and without the 300 mm beam-line to compare the effects of beam divergence on the solid target (FIGS. 1 and 2). The experiment was conducted using both H− ion sources with different ion-to-puller extraction gaps (ion source 1 is 1.55 mm with ion source 2 at 1.90 mm). The setting of the ion-to-puller gap changes the focusing of the accelerated beam inside the cavity. Results and Discussion The segmented beam model was used to calculate the temperature on and within the target, as well as the maximum temperature of the bulk material. The first segment is the leading segment of the material irradiated by the incident proton beam. Results are shown in TABLE 2. Target temperatures were measured experimentally under two different conditions; target attached at the end of a 300mm beam-line and target attached directly to the cyclotron. The temperature was measured experimentally using the platinum disk with 2 thermocouples inside the bulk target material irradiated on the end of a 300mm beam-line. The measured temperature is shown in TABLE 2. The variation between ion source 1 and 2 for the temperature measured in the center was 11–15 %, while the variation on the radial position was 2–6 %. A smaller ion-to-puller extraction distance (ion source 1) reduces the cross-sectional area of the accelerated beam; the consequent high proton current density (10mm diameter collimated beam) increases the temperature inside the bulk material for a fixed target current. The highest observed radial temperature was 93 °C, with target current of 50 μA using ion source 1. This is well below the melting point for the o-ring seal. The temperature measured experimentally using the same platinum disk with no beam-line is shown in TABLE 4. A temperature difference of up to 7 % was measured between ion source 1 and 2 at the exit port without the beam-line, while the maximum variation on the radial position was 3 %. A comparison between the calculated theoretical and measured temperatures is shown in FIGS. 3 to 6. The temperatures calculated by the FEA model underestimate the temperature regardless of target position (with or without the beam-line) and for both ion sources. The temperature difference between the FEA model and the experimental results increases with increasing target currents. As shown in Figure 3, at the target center the FEA model underestimated the temperature by 22–32 % for ion source 1 and 13–22 % for ion source 2. This is consistent with the difference between the two ion sources due to the difference in the ion-to-puller gap size. With the target mounted at the exit port the theoretical and measured temperature for the center of the platinum disk is shown in FIGURE 4. The FEA model underestimates the temperature at the center of the platinum disc by 2–10 % for both ion sources. As shown with the previous experiment, the margin of error increases with increasing target current. Comparison between FIGS. 3 and 4 shows the measured temperature at the center of the platinum disk is significantly lower when the target is attached to exit port of the cyclotron. Localised area of high current density (hot spots) is not registered as higher temperature in the bulk material. True temperature inside the bulk material is highly dependent on the thermal conductivity of the target material and the resolution of the thermocouple. The cross-sectional area of the beam ‘hot-spot’ will be greater due to beam divergence at the end of the beam line compared with the exit port. The ‘hot’ area of the expanded beam becomes a significant portion of the overall collimated beam (collimator dia. 10.0 mm). A more uniform beam profile (less heterogeneity) evenly distributed the area of high current density across the disk surface, effectively increasing the temperature of the bulk material while decreasing the sensitivity required to measure the true temperature. As observed from this comparative study it appears that a more homogeneous current density leads to a higher temperature measurement at the target center. With the solid target at the end of the beam-line, target current lost on the collimator and beam-line was >55%. The effect of beam divergence is clearly observed in TABLE 5. With the target mounted directly at the exit port the current lost was reduced to < 40 %. Although the average proton current density is the same for any set target current, irrespective of target position, the contribution of the peripheral beam to the total target current should not be underestimated. A loss of ~40 μA on the collimator and beam-line places greater reliance on the center of the ‘hot’ beam to maintain the same target current. The temperature at the radial position (FIG. 5) observes the same trend as for the temperature measured in the center. The error increases for higher target currents and the FEA model underestimated the temperature by 19–40 %. The error at this location is due partly to the model’s assumption of a uniform heat source, applied to the material on a single axis (perpendicular to the material surface) and does not account for any scattering or divergence of the incident proton beam. FIGURE 6 shows that the FEA model underestimated the radial temperature by 16–37 %, when the target is connected to the exit port, for reasons discussed previously. Comparison with FIG. 5 (target on the beam-line) shows the same margin of error between the FEA and the experimental results (19–40 %). The temperature difference between the FEA model and measured temperature at the radial position is independent of the beam profile and beam divergence. The FEA model underestimated the temperature at the radial location with or without the beam-line and for both ion sources. The significance difference in temperature between the FEA model and the experimental is due to our model assumption that the maximum radial temperature is on the irradiated surface and not inside the material corresponding to the layer with the maximum energy lost. In addition, the FEA model does not ac-count for the divergence of the proton beam as it travels through the material. Given the temperature at 50 μA target current is > 90 °C (TABLES 3 and 4) we have capped the experi-ment below this point to prevent any damage the o-ring seal. Conclusion The segmented FEA model was inadequate in determining the temperature for the target at the end of a 300mm beam-line (> 30 % difference). A combination of beam divergence and greater uniform coverage of high current density beam resulted in a higher than predicted temperature reading. However, the segmented FEA model provides a good estimation (< 10 % difference) for the observed temperature of the bulk material at the exit port. The simplistic FEA model was unable estimate the temperature at the radial position (~ 40 % difference) regardless of ion source or target position. A comparison between the two ion sources with different ion-to-puller extraction gap, leading to different focusing of the accelerated beam yield minimal temperature difference. Although a 15% difference was observed between the ion sources at the end of the beam-line, a major contributing factor is beam divergence beyond the magnetic field rather than the beam size of the accelerated beam. Further studies are underway to determine the beam profile (quantitatively using radiographic film), quantify the contribution of the peripheral beam to the total beam current by comparing different size collimators and to investigate other FEA models by applying different beam models (heterogeneous and homogeneous beam) and different heat sources (surface vs. volumetric). Currently the RAPID Lab solid targetry is placed at the end of the beam-line for easy loading and unloading, since multiple target irradiations are performed per month2. However, RAPID is presently developing a new solid targetry sys-tem which eliminates the need for a beam-line and will be able to manage a maximum extracted target current of 150 μA.

Recent research on jointed unbonded post-tensioned precast concrete frames has demonstrated their superior seismic resistance. Inelastic rotation generated during large earthquake motions is accommodated through gap opening and closing at the beam-to-column connections in the frame. By applying the principles of Damage Avoidance Design (DAD), a steel-steel armoured connection has been demonstrated to be effective in protecting the precast elements from damage. The re-centring ability of the unbonded prestressed post-tensioned system allows the building to return to its original undeformed position after the earthquake with negligible residual deformations. This research experimentally assesses the biaxial performance of the unbonded precast beam-to-column joint and simplifies the steel-steel armoured connection details in the joint. The experimental results of both quasi-static unidirectional lateral loading tests and biaxial lateral loading tests conducted on a 80% scaled unbonded jointed beam-to-column joint are presented. The performance of the proposed simplified steel-steel connection is assessed. A theoretical model is developed based primarily on rigid body kinematics and is validated using the test results. A formulation is also developed based on St Vennants' principle, to estimate the effective stiffness of the precast concrete beams under bidirectional rocking. Based on the experimental findings, improvements to the steel-steel armoured connection and joint details are proposed.

Reinforced concrete structures designed in pre-1970s are vulnerable under earthquakes due to lack of seismic detailing to provide adequate ductility. Typical deficiencies of pre-1970s reinforced concrete structures are (a) use of plain bars as longitudinal reinforcement, (b) inadequate anchorage of beam longitudinal reinforcement in the column (particularly exterior column), (c) lack of joint transverse reinforcement if any, (d) lapped splices located just above joint, and (e) low concrete strength. Furthermore, the use of infill walls is a controversial issue because it can help to provide additional stiffness to the structure on the positive side and on the negative side it can increase the possibility of soft-storey mechanisms if it is distributed irregularly. Experimental research to investigate the possible seismic behaviour of pre-1970s reinforced concrete structures have been carried out in the past. However, there is still an absence of experimental tests on the 3-D response of existing beam-column joints under bi-directional cyclic loading, such as corner joints. As part of the research work herein presented, a series of experimental tests on beam-column subassemblies with typical detailing of pre-1970s buildings has been carried out to investigate the behaviour of existing reinforced concrete structures. Six two-third scale plane frame exterior beam-column joint subassemblies were constructed and tested under quasi-static cyclic loading in the Structural Laboratory of the University of Canterbury. The reinforcement detailing and beam dimension were varied to investigate their effect on the seismic behaviour. Four specimens were conventional deep beam-column joint, with two of them using deformed longitudinal bars and beam bars bent in to the joint and the two others using plain round longitudinal bars and beam bars with end hooks. The other two specimens were shallow beam-column joint, one with deformed longitudinal bars and beam bars bent in to the joint, the other with plain round longitudinal bars and beam bars with end hooks. All units had one transverse reinforcement in the joint. The results of the experimental tests indicated that conventional exterior beam-column joint with typical detailing of pre-1970s building would experience serious diagonal tension cracking in the joint panel under earthquake. The use of plain round bars with end hooks for beam longitudinal reinforcement results in more severe damage in the joint core when compared to the use of deformed bars for beam longitudinal reinforcement bent in to the joint, due to the combination of bar slips and concrete crushing. One interesting outcome is that the use of shallow beam in the exterior beam-column joint could avoid the joint cracking due to the beam size although the strength provided lower when compared with the use of deep beam with equal moment capacity. Therefore, taking into account the low strength and stiffness, shallow beam can be reintroduced as an alternative solution in design process. In addition, the presence of single transverse reinforcement in the joint core can provide additional confinement after the first crack occurred, thus delaying the strength degradation of the structure. Three two-third scale space frame corner beam-column joint subassemblies were also constructed to investigate the biaxial loading effect. Two specimens were deep-deep beam-corner column joint specimens and the other one was deep-shallow beam-corner column joint specimen. One deep-deep beam-corner column joint specimen was not using any transverse reinforcement in the joint core while the two other specimens were using one transverse reinforcement in the joint core. Plain round longitudinal bars were used for all units with hook anchorage for the beam bars. Results from the tests confirmed the evidences from earthquake damage observations with the exterior 3-D (corner) beam-column joint subjected to biaxial loading would have less strength and suffer higher damage in the joint area under earthquake. Furthermore, the joint shear relation in the two directions is calibrated from the results to provide better analysis. An analytical model was used to simulate the seismic behaviour of the joints with the help of Ruaumoko software. Alternative strength degradation curves corresponding to different reinforcement detailing of beam-column joint unit were proposed based on the test results.