System evaluation of automated production and inhalation of 15O-labeled gaseous radiopharmaceuticals for the rapid 15O-oxygen PET examinations
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15O-oxygen inhalation PET is unique in its ability to provide fundamental information regarding cerebral hemodynamics and energy metabolism in man. However, the use of 15O-oxygen has been limited in a clinical environment largely attributed to logistical complexity, in relation to a long study period, and the need to produce and inhale three sets of radiopharmaceuticals. Despite the recent works that enabled shortening of the PET examination period, radiopharmaceutical production has still been a limiting factor. This study was aimed to evaluate a recently developed radiosynthesis/inhalation system that automatically supplies a series of 15O-labeled gaseous radiopharmaceuticals of C15O, 15O2, and C15O2 at short intervals.
The system consists of a radiosynthesizer which produces C15O, 15O2, and C15O2; an inhalation controller; and an inhalation/scavenging unit. All three parts are controlled by a common sequencer, enabling automated production and inhalation at intervals less than 4.5 min. The gas inhalation/scavenging unit controls to sequentially supply of qualified radiopharmaceuticals at given radioactivity for given periods at given intervals. The unit also scavenges effectively the non-inhaled radioactive gases. Performance and reproducibility are evaluated.
Using an 15O-dedicated cyclotron with deuteron of 3.5 MeV at 40 μA, C15O, 15O2, and C15O2 were sequentially produced at a constant rate of 1400, 2400, and 2000 MBq/min, respectively. Each of radiopharmaceuticals were stably inhaled at < 4.5 min intervals with negligible contamination from the previous supply. The two-hole two-layered face mask with scavenging device minimized the gaseous radioactivity surrounding subject’s face, while maintaining the normocapnia during examination periods. Quantitative assessment of net administration doses could be assessed using a pair of radio-detectors at inlet and scavenging tubes, as 541 ± 149, 320 ± 103, 523 ± 137 MBq corresponding to 2-min supply of 2574 ± 255 MBq for C15O, and 1-min supply of 2220 ± 766 and 1763 ± 174 for 15O2 and C15O2, respectively.
The present system allowed for automated production and inhalation of series of 15O-labeled radiopharmaceuticals as required in the rapid 15O-Oxygen PET protocol. The production and inhalation were reproducible and improved logistical complexity, and thus the use of 15O-oxygen might have become practically applicable in clinical environments.
Keywords15O-labeled oxygen (15O2) 15O-labeled carbon dioxide (C15O2) PET Oxygen extraction fraction Cerebral metabolic rate of oxygen
Arterial input function
Area under the curve
Cerebral blood flow
Cerebral blood volume
Cerebral metabolic rate of oxygen
Mass flow controller
Maximum intensity projection
Molecular Sieve 5A
Oxygen extraction fraction
Radio water generator
15O-oxygen (15O2) PET is unique in its ability to provide fundamental information regarding cerebral hemodynamics and energy metabolism in man, which has proven central to understanding cerebral oxidative glycolysis in many pathologies, and it is considered the gold standard for identifying cerebral ischemia. Specifically, it has been utilized to quantitatively assess the regional cerebral metabolic rate of oxygen (CMRO2) and the regional oxygen extraction fraction (OEF) [1, 2]. In typical protocols, additional PET imaging had to be carried out in order to assess cerebral blood flow (CBF) using intravenous 15O-labeled water (H215O) or inhalation of carbon dioxide (C15O2), and cerebral blood volume (CBV) using inhalation of 15O-carbon monoxide (C15O). The technique has contributed to the understanding of pathophysiology and to the development of guidelines for treating patients with stroke and cerebral vascular diseases . More recently, a series of studies demonstrated that the aerobic glycolysis as characterized by means of a combined 18F-fluorodeoxyglucose (FDG) and 15O-oxygen PET imaging are related to malignancy in brain tumor , and also to potential alterations of the oxidative phosphorylation in patients with dementia  and more specifically with the amyloid deposition in Alzheimer disease [4, 5, 6].
Typical procedures in a PET examination with 15O-oxygen inhalation are labor intensive and have not been considered practical if one intends to utilize it in a clinical environment, largely attributed to the need for producing three different radiopharmaceuticals labeled with 15O in parallel to PET imaging . Typical methods of the “three-step autoradiograph”  and the “steady-state method” [9, 10, 11] require an hour or even more for a full examination, during which the arterial blood sampling has often been needed with plasma separation to assess the radioactivity concentrations of 15O2 and H215O in the arterial blood during the PET scan. Naive corrections are needed for radioactivity decay, and for the delay and dispersion of the arterial blood radioactivity curves [12, 13]. It should also be noted that quantitative imaging during inhalation of radioactive gases was challenging when using a three-dimensional (3D) PET scanner due to the increased random and scattered events originated from the gaseous radioactivity surrounding the patient face. Furthermore, internal radiation is also a legitimate concern for clinical staff unless a system is established to prevent unnecessary leakage of radioactive gases during patient inhalation while maintaining the normocapnia.
Recently, significant progress has been reported in the instrumentation and reconstruction software implemented in commercial 3D PET scanners. High-speed electronics offer precise data acquisition with considerably reduced random events. Consequently, the accuracy and signal-to-noise ratio are greatly improved , allowing theoretical model-based scatter compensation [15, 16, 17, 18, 19, 20] to be accurately applied. A markedly improved performance in 3D PET is essential for better image quality and increased accuracy, while simultaneously reducing the radiation dose in patients . It has also been demonstrated that the degradation in the quantitative accuracy has been resolved even during the inhalation of 15O-gases in 3D PET by means of the improvement of the scatter correction procedures , suggesting that the arterial input function (AIF) assessed with arterial blood sampling may be replaced by the image-derived AIF . It should be noted that the kinetic model for 15O-oxygen has been well validated . This also support the adequacy of a sophisticated kinetic formulation which shortens the PET examination period, by means of a 6–9 min single dynamic PET imaging while 15O2 and H215O (or C15O2) are sequentially administered [25, 26]. Such a method has been well validated to provide quantitative OEF values that were consistent with those determined from the arterial-venous difference of oxygen contents in experimental animals (monkeys) for a wide physiological range .
The logistical complexity remains the major limitation in producing a series of 15O-labeled radiopharmaceuticals. The authors then hypothesized that this may be overcome by using an automated system that enables sequential production and inhalation of the 15O-labeled radiopharmaceuticals with minimal human operation and recording of all signals from the radiopharmaceutical production/inhalation system, and other peripheral equipment utilized in the 15O-Oxygen PET experiment. Recently, a system has been developed to produce and inhale a series of 15O-labeled radiopharmaceuticals of C15O, 15O2, and C15O2 sequentially with minimal human operations, as required in given protocols of the three-step autoradiography  and the rapid protocol of Kudomi et al. [25, 26]. The system for the radiopharmaceutical production and inhalation has been approved as a medical device in authors’ country, and contributed to clinical examinations on more than 2500 patients. The present study was then aimed to evaluate retrospectively the reproducibility of production and inhalation of radiopharmaceuticals, when applied to the ultra-rapid 15O-oxygen PET examinations. We then investigated the radioactivity recovery, and chemical and radiochemical purity in the 15O2 and C15O productions for different carrier gas concentrations. We further evaluated impact of reducing the leakage of radioactive gases from the inhalation face mask, and potential ability to estimate the administration dose to individual patients.
Materials and methods
The automated radiosynthesis/inhalation system approved as a medical device in November 2012 in authors’ country has been utilized on more than 2500 clinical scans with 15O-oxygen inhalation following the protocol of Kudomi et al. . Basic performance including the recovery, and chemical and radiochemical purity was evaluated for each of three gaseous radiopharmaceuticals of C15O, 15O2, and C15O2. Data previously conducted as clinical examinations between November 20, 2012 and March 31, 2015 (2.4 ± 1.2 examinations per day) were retrospectively analyzed. The data were from PET examinations on 749 patients, and included (a) the time chart log of the radiosynthesizer, which includes the time-radioactivity curves of the radio-detectors and gas chromatograms; (b) AIF recorded by the functional image calculation software; (c) record of Capnometer; (d) records of the time-radioactivity curves of the area monitor in a PET room, of the air in the exhaust duct from a PET area, and the cyclotron area; and (e) radioactivity curves of a pair of beta-ray detectors placed each of inlet and scavenge tubes of the facemask with the flow values for each tubes. The patients were 433 males and 316 females with a body weight of 60.4 ± 11.4 kg and an age of 59.8 ± 26.0 years old. The study was approved by the Ethics Committee at the authors’ institution with the approval number M30-013 for retrospective data analysis on clinical data and M22-089-2 for PET imaging on healthy volunteers.
Each radioactive gas was continuously circulated during the beam bombardment to the target from the cyclotron target to the radiosynthesizer, the inhalation controller, and to a decay tank (tank 1, in Fig. 1). Radiopharmaceuticals were then supplied to the patient’s face mask from the inhalation controller for a specified period at the prescribed supply rate for each radiopharmaceutical in units of MBq/min, which can be adapted to a short-period inhalation protocol such as three-step autoradiography [8, 27] or a continuous supply as required in the steady-state method [11, 28]. The target chamber was actively evacuated at the end of each radiopharmaceutical supply to minimize the intervals between sequential inhalations of different radiopharmaceuticals. Due to avoidance contamination from the previous supply, the system can be applied to the multiple tracer approaches of Kudomi et al. [25, 26]. The production and supply of a series of 15O-gaseous radiopharmaceuticals were controlled by a sequencer, which allowed for automatic production. The system was also designed to accommodate changes in the order of sequential radiopharmaceutical productions, the amount of radioactivity, and the period of the inhalation. This study employed a fixed protocol in which where the radiosynthesis and in halation was first C15O followed by a sequential supply of 15O2 and C15O2 at a 4.5-min interval.
The system recorded all mechanics operations and count rates of the radioactivity detectors and flow values, which were transferred to the workstation to confirm the consistency with the PET data. Additional data were also recorded from other peripheral devices utilized during the PET examination, namely the arterial input function detector , a well counter, a Capnometer, and a pair of radioactivity detectors for inlet and scavenge tubes of the patient facemask. All these data were stored in a common workstation, and were used for quality assurance of the entire PET examination procedures.
Due to the requirement for radiation safety regulation in the authors’ country, air of the entire PET room was actively exhausted at a flow rate of approximately 2000 m3 per hour, which corresponded to 17–20 air changes per hour. The exhausted air from other four rooms was gathered into a single duct. Total air flow was approximately 7000 m3/h, as assessed according to the authorized procedures of JIS A1413 (equivalent to a proposed ISO 16640) using a hybrid flow meter (DP70, Hiyoshi-Denki, Yokohama City, Japan). A calibrated gamma-ray monitor (DGM-151, Hitachi-Aloka, Tokyo, Japan) was placed inside the exhaust duct to monitor the gaseous radioactivity carried from the PET room, and also from the entire facility during the PET examination period.
15O-radioactivity and the radiosynthesis of C15O, 15O2, and C15O2 followed the method described by Clark and Buckingham . Briefly, 15O was produced by the 14N(d,n)15O nuclear reaction in the cyclotron target, in which the target gas to produce 15O2 was nitrogen (N2) containing oxygen (O2) as a carrier gas. The concentration of the carrier gas of O2 was chosen at 0.3% in all clinical studies according to a systematic evaluation in this study (see below). The 15O2 produced in the target was carried to a soda lime column to remove contamination, which was mostly C15O2. C15O2 was produced also in the target filled with N2 containing 1.0% of CO2. The C15O2 produced in the target was funneled to a charcoal column heated to 430 °C to remove contamination of C15O. C15O was synthesized from the 15O2 gas by carrying it away from the target into a charcoal column heated to 1000 °C. A soda lime column was then used to remove contamination, mostly C15O2. Each of the radioactive gases produced were continuously carried to the inhalation controller placed in the PET scanner room during deuteron beam bombardment and then to a compressing tank (tank 1 in Fig. 1). The flow rates to the radiosynthesizer from the target and to the inhalation controller were controlled by a mass flow controller (MFC) (MFC1 set at 500 mL/min).
Immediately after the end of each radiopharmaceutical production, the cyclotron beam was stopped. Then the target chamber was evacuated at a negative pressure using a rotary pump for a preset period of 18 s. The target chamber was then filled with a new target gas, and was exposed to the deuteron beam for the next radiopharmaceutical production.
While the synthesizer was producing radioactive radiopharmaceuticals, a radioactive gas was carried to the inhalation controller installed in the PET room and circulated to the waste tank (tank 1) in the cyclotron room. This gas was released from tank 1 after sufficient decay. The inhalation controller then supplied radioactive radiopharmaceuticals to a patient’s face mask according to the given protocols. In the clinical protocols at our institution, the supply flow rate defined as (F2 + F4) was 1000 mL/min by controlling MFC2 and MFC4. The radioactivity supply rate, defined as F2 × R1, was at approximately 1300 MBq/min, 2400 MBq/min, and 2000 MB/min, respectively. The supply period for each radiopharmaceutical was 2 min, 1 min, and 1 min, yielding the total radioactivity supply, defined as (F2 + F4) × R2 × the supply period, was to be 2600 MBq, 2400 MBq, and 2000 MBq corresponding to C15O, 15O2, and C15O2, respectively.
A gas chromatograph in the inhalation controller was aimed to confirm radiochemical and chemical purity, including contaminations of residual radiopharmaceuticals from the previous administration. A small gas sample was collected to assess the radiochemical and chemical purity using two small rapid gas chromatographs (CP-490, Agilent Technologies, Santa Clara, CA, USA), implemented Molecular Sieve 5A (MS) at 120 °C and Pora-Plot Q (PPQ) at 60 °C with capillary columns that are 10 m long, respectively. The gas samples were taken prior to each initiation of the radiopharmaceutical supply.
Scavenged air was compressed into tank 2, which consisted of four of 200-L tanks, where the storage was automatically changed among the tanks, each of which was released after sufficient decay. Capnometer (MSC8000, Contec Medical Systems, Hebei Provience, China) was used to monitor the end-tidal carbon dioxide partial pressure and the respiration rate during PET scanning. The tube for this Capnometer was also used to supply radioactive gases through a small-diameter tube into a space inside the inner layer of the facemask between the nose and the mouth.
Radio water generator unit
A radio water generator (RWG, HIDEX co, Turku, Finland) was placed in parallel to the 15O-oxygen production/inhalation system (see Fig. 1). 15O2 gas was continuously produced in the cyclotron target, and was mixed with a 5% H2 before the furnace heated at 700 °C to produce H215O in the cyclotron room. The gas containing H215O was then continuously circulated to a decay tank (tank 1) via the RWG unit installed in the PET room (Fig. 1). The radioactive H215O was then transferred to the saline through a membrane cassette in the RWG device. The radioactive H215O was continuously circulated to an outlet tube, from which a given amount of radioactive saline could be administered into the patient’s vein at the prescribed dose for a given period. A syringe sample of H215O could also be taken from this tube, for an experimental use such as calibration, and quality assessment.
All experiments and clinical scans were carried out by a deuteron beam bombardment of 40 μA on a target. The pressure of the target gas was 0.08 MPa. The flow rate of MFC1 in the synthesizer was 500 mL/min, and the supply flow rate to the face mask (MFC2 + MFC4) was 1000 mL/min.
The recovery and the dependency on the carrier gas concentration of O2 was evaluated for a production of gaseous 15O2, and consequently synthesized gaseous C15O and H215O in saline. The experiment was carried out for a target gas of N2 containing 0.3%, 0.5%, and 1.0% carrier gas of oxygen (O2). 15O2 and C15O were continuously produced and carried to the inhalation unit. The radioactivity recovery was determined for a 1-min supply for both 15O2 or C15O. Gaseous 15O2 was also carried to RWG to generate H215O saline, and the recovery was determined for 1-min sampling of H215O in the saline. The radioactivity recovery of C15O2 was also assessed similarly using a target gas containing 1.0% carbon-dioxide (CO2) in N2. The radiochemical purity and non-radiochemical purity were assessed for each of C15O, 15O2, and C15O2 productions. These measurements were repeated six times for each radiopharmaceutical.
The radiochemical contamination was determined in the second administration namely C15O2 when the sequential 15O2–C15O2 inhalation protocol at 4.5-min interval was utilized as employed in the clinical examination. The radioactivity was assessed with and without producing the second radiopharmaceutical of C15O2. This experiment was also repeated six times.
Retrospective analysis was carried out using the data recorded for 749 subjects who underwent all C15O, 15O2, and C15O2 inhalation scans according to the fixed protocol, with inhalation periods of 2 min for C15O, and 1 min for 15O2 and C15O2. Radioactivity supply as calculated as an integral of the radioactivity concentration in the supply tube multiplied by its flow rate, and the net administration as calculated as an integral of the radioactivity concentration in the scavenging tube multiplied by its flow rate for each of C15O, 15O2, and C15O2 inhalation scans. The net administration dose was then calculated as a subtraction of those two values for each radiopharmaceutical. Reproducibility of supply and net administration dose among subjects were evaluated. Time-dependent net administration radioactivity was also compared with the arterial input function (AIF) estimated from the continuously monitored arterial radioactivity time-activity curves (TACs).
The effective administration dose was divided by the body weight of the patient for the C15O2 inhalation scan and was compared with AUCs of the directly assessed AIF for each patient scan. It should be noted that the delay and dispersion were carefully compensated in AIFs as described in earlier works [12, 13, 30]. The integration period was set for the early period of 150 s after initiation of C15O2 inhalation.
Scavenging effectiveness of the two-hole two-layered facemask was evaluated on reconstructed tomographic and maximum intensity projection (MIP) images during 15O2 and C15O2 inhalation periods. Evaluation was also carried out on functional images of CBF, CMRO2, and OEF calculated according to two mathematical formulations, i.e., the DARG method  (Fig. 9a) and DBFM method  with a modification to estimate the arterial vascular components for both H215O and 15O2, denoted as V0W and V0O, respectively.
Leakage of the 15O-gaseous radioactivity to the PET room was calculated using the detector placed in the exhaust duct from the PET room, which was calibrated to the common dose calibrator utilized in our PET examination so that the detectors’ sensitivity was consistent with that of supply from the radiosynthesis/inhalation device. The known background level of 0.020 Bq/mL was subtracted from the observed counting rates of the detector in the exhaust duct. The total radioactivity from the PET room was then calculated by multiplying the flow rate of the duct. The radioactivity curves were then corrected for the radioactive decay of 15O at each time point back to the inhalation initiation time. The clearance of the gaseous radioactivity was interpolated by a single exponential function with a half-life of 3.5 min, which corresponded to 17 changes of the air in the PET room per hour, as estimated from the room volume and the flow rate. AUCs of the radioactivity concentration curves were calculated for a period of each radio-gas supply, and were then divided by the amount of radioactivity supply to each patient, so as to estimate the %leakage for each administration.
All data were presented as the mean ± 1 s.d. Pearson’s correlation analysis and linear regression analysis were used to evaluate the relationships between the two values. A value of p < 0.05 was considered statistically significant.
Radioactivity yields of C15O and 15O2 gases and H215O saline for three different oxygen concentrations in nitrogen as the target gas
Oxygen concentration in nitrogen
1757 ± 146*
2634 ± 145
731 ± 16
1974 ± 39
2733 ± 60
735 ± 41
2043 ± 69
2749 ± 72
742 ± 14
Chemical concentration and radiochemical purity
98.77 ± 0.52
99.00 ± 0.43
98.99 ± 0.55
0.60 ± 0.06
0.10 ± 0.07
0.04 ± 0.01
0.64 ± 0.56
0.91 ± 0.40
0.99 ± 0.55
0.03 ± 0.03
0.01 ± 0.03
0.82 ± 0.11
Summary of the supply and net administration doses, and the leakage from the face mask system
Supplied radioactivity per scan
2574 ± 255 MBq
2220 ± 766 MBq
1763 ± 174 MBq
Net administration per scan
541 ± 149 MBq
320 ± 103 MBq
523 ± 137 MBq
0.166 ± 0.493%
0.181 ± 0.525%
0.148 ± 0.545%
# of scans with no detected leakage
# of scans
The present study demonstrated that the novel radiosynthesis system was able to produce and supply a sufficient amount of a series of 15O-labeled radiopharmaceuticals of C15O, 15O2, and C15O2 by combining it with the 15O-dedicated small cyclotron of C3D when a deuteron beam was accelerated at a beam current of 40 μA (Tables 1 and 3). The radiochemical purity was sufficiently high with acceptable chemical contaminations (Table 2). The sequencer-controlling radiosynthesis and the inhalation controller allowed a reliable operation and fairly good reproducibility in the production and inhalation of a series of radiopharmaceuticals. The radiochemical contamination was shown to be negligibly small even when the radiopharmaceuticals were supplied at 4.5-min intervals (Fig. 4). These features allowed the recently developed rapid method of Kudomi et al.  applicable to PET imaging under the clinical environment, as has been demonstrated in more than 2500 examinations in our facility since December, 2012. Automatic evacuation of the target gas that was carried immediately after the end of production of a previous radiopharmaceutical was effective to reduce contamination from the previous supply in the second production despite of the short interval. Automatic record of radioactivity detectors, electronic valves, flow meters, the pressure monitoring sensors, together with other monitoring devices needed in PET examinations were aimed to ensure the quality of 15O-labeled radiopharmaceuticals in routine clinical scans. This feature would assist the quality of radiopharmaceuticals as a part of the good manufacturing practice (GMP), and the standardization of PET examination.
An important outcome of the inhalation/scavenging unit implemented in this system was the ability to remove radioactivity from the area inside the FOV of PET imaging by effectively scavenging the non-inhaled radioactive gases from the outer layer of the two-hole two-layered face mask (Fig. 2), while a sufficient amount of radiopharmaceuticals were confined in a patient nose/mouth area as demonstrated in Figs. 8 and 9. It was shown earlier that the present inhalation/scavenging unit was effective to suppress the random rates which might be caused by a relatively strong gaseous radioactivity, contributing to reduced dead-time, and thus improved quantitative accuracy with minimal enhancement of image noise, as shown in our earlier study . It is also important to note that the improved accuracy of PET images during the gaseous 15O-labeled radiopharmaceuticals may enable the determination of AIF from radioactivity concentration curves in the carotid arterial region. This may further provide opportunity of a non-invasive quantitation of functional parametric images without the arterial blood sampling . Systematic study should be carried out to evaluate the adequacy of the non-invasive quantitation in 15O-oxygen PET scans.
The scavenged gaseous radioactivity was compressed and stored in the decay tank (tank 1 in Fig. 1), until it decayed sufficiently prior to releasing it to the atmosphere. This was aimed to prevent from the radiation of not only staff working in the PET facility but also a public living outside of the facility. It is also important to note that use of the present inhalation/scavenging unit allowed for a stable respiration or normocapnia during an entire PET examination period, as typically seen Fig. 5c. It has been reported that only a change of 1.0 mmHg in PaCO2 causes a change by 6% in CBF , but the present system allowed only a small change in EtCO2, which is an indirect marker of PaCO2, between 15O2 and C15O2 inhalation periods, e.g., 0.5 ± 1.0 and − 0.6 ± 2.5 mmHg, corresponding to healthy and patient populations, respectively. The variations in EtCO2 of ± 1.0 mmHg between the 15O2 and C15O2 inhalation periods in healthy controls were practically the same. In the entire subjects including the patient population, the variation was larger and reached to ± 2.5 mmHg, which was attributed to the unstable breathing. As typically shown in Fig. 6, more than 10% of patients displayed AIFs with a zigzag shape, which was due to unstable breathing. The net administration curves and AIFs were less reproducible among subjects in patient populations, as also seen in EtCO2 curves which were unstable in patients. The transient change in PaCO2 during the PET examination would still be in an acceptable range in order to reliably quantify CBF and CMRO2 in clinical settings. Continuous supply of a fresh air to the two-hole two-layered facemask assisted easy breathing despite of prevention from the leakage of radiopharmaceuticals, as seen in Fig. 5c.
It can be seen from Fig. 7 that the net administration dose can be estimated as the difference in the radioactivity between the inlet and outlet tubes for the C15O2 inhalation scan. Transient changes in inhaling the gaseous radiopharmaceuticals suggested that population-based AIFs were limited in terms of providing individual AIFs. It should also be noted that the net administration might be overestimated when 15O2 is inhaled, because 15O2 stays longer as a gaseous form in the lung cavity than C15O2 and C15O before transported to the blood circulation. This could be modeled, but it is beyond of the scope of the present study. Further studies need to be carried out.
A larger radioactivity in the nasal cavity during C15O2 inhalation is attributed to the solubility of carbon dioxide compared to that of 15O2, though this did not have a significant contribution to degrade the image accuracy or image quality. A higher accumulation of C15O2 into the brain than that of 15O2 is attributed to the higher extraction of gaseous radioactivity in the lung to the blood circulation, and also to a higher first-pass extraction rate of H215O than that of 15O2 in the brain. Larger radioactivity inside the facemask during the 15O2 inhalation than that during C15O2 inhalation could be explained by a smaller extraction rate of 15O2 in the lung than that of C15O2. The gamma detector curves in the PET room showing a sharper peak or faster clearance after the 15O2 inhalation than that of C15O2 and that of C15O was attributed to the smaller fraction of inhaled 15O2 were absorbed in the lung being transferred to the blood circulation. In other words, more amount of 15O2 was scavenged from the facemask, than other radiopharmaceuticals.
It is worth noting that the chemical contamination of non-radioactive carbon-monoxide in the C15O radiopharmaceutical varies dependent of the carrier gas concentration of oxygen in the target gas. This is because the total amount of carbon-monoxide becomes double of the oxygen content as two molecular units of CO are produced from one O2 molecule by combining it with two carbons in the charcoal column. The use of 0.3% of cold oxygen in nitrogen gas should therefore be encouraged to minimize the toxicity of the carbon-monoxide contamination instead of 0.5% or 1.0% O2, which produces 1.0% or 2.0% of CO, respectively. This study demonstrated that the radioactivity yields were not significantly different in the 15O2 and H215O production, although the production of C15O was reduced, but only approximately 10%, which should not cause significant problems in practical examinations.
The present study demonstrated that the average leakage was 0.17 ± 0.65% from the facemask as estimated in this study including corrections for backgrounds and the decay (Fig. 10). Due to the regulation required by the radiation safety authority in this country, the room air had to be evacuated at approximately 2000 m3 per hour to the exhaust ducts, which corresponded to 17 times of exchanging the entire air in the PET room. Such strong evacuation may not be needed by using the present two-hole two-layered facemask with active scavenging. Use of the decay tank, tank2 in Fig. 1, should be encouraged in order to minimize the leakage to the room in the facility and also to the public. The International Commission on Radiological Protection (ICRP) does not define the upper limit of radioactivity nor a radioactivity concentration at the exhaust duct for short half-life radio-nuclei in gaseous form. This is because the public safety may be guaranteed by stopping the room exhaust if significant leakage occurs. In such a situation, the workers in the facility would have to leave from the area to prevent from a high risk of radiation. However, this is not practically adequate, because clinical examinations are carried out on patients inside the facility. To reduce the radioactivity released from the exhaust duct to the public, the use of decay tank was shown to be effective, in which use of the facemask that prevents from the leakage to the room was essential. The present inhalation/scavenging unit which reduced the leakage to the order of 0.1% was essential when utilizing the gaseous 15O-oxygen radiopharmaceuticals in clinical PET examinations.
The present study demonstrated that the recently developed system for automated production and inhalation of a series of 15O-labeled gaseous radiopharmaceuticals produced enough amount of C15O, 15O2, and C15O2 at a reasonably short interval with sufficiently high radiochemical purity as required for clinical use. It is also important to note that logistical complexity in terms of producing and inhaling three sets of 15O-Oxygen-labeled radiopharmaceuticals has been considerably improved. This is particularly essential when a recently proposed rapid protocol of Kudomi et al.  is utilized under clinical environment. Functional parametric imaging of CBF, CMRO2, and OEF can therefore be obtained from a short scan period of 8 min, with considerably reduced work load of clinical staff as compared with previous PET examination systems. Effective scavenge allow for accurate quantitation using a commercial PET scanner in 3D mode. Minimal leakage from the facemask should contribute to reduction of unnecessary radiation for workers and for public.
We are indebted to the staff from the Department of Radiology, National Cerebral and Cardiovascular Center, Osaka, Japan. We are thankful to Mr. Yoshitaka Sanda from JFE Inc. (Tokyo, Japan) for his help with data sorting of the radioactivity concentration curves installed at the exhaust duct and to Mr. Yoshinori Miyake from the Department of Investigative Radiology, National Cerebral and Cardiovascular Center Research Institute, for his help with the experimental setup to evaluate the present system.
The present work was supported by a grant from the Ministry of Health, Labor and Welfare, Japan, and grant from Japan Agency for Medical Research and Development.
Availability of data and materials
Datasets would be made available for usage in scientific works on request to the author.
SI, TM, and MY equally contributed to this work as the first Author. SI participated in the design, created the program, implemented the analysis, and drafted the manuscript. TM, MY, YH, and KK participated in the design, created the system, optimized the technique, created the program, analyzed the results, and edited the manuscript. KT, JT, and SS participated in the design and edited the manuscript. YT participated in the data collection and image processing. TF, JN, and JT participated in design, patient recruitment, and edited the manuscript. SK participated in the design and edited the manuscript. HI participated in the design, managed the study, designed the technique, and drafted the manuscript. All authors reviewed and agreed to the manuscript content. All authors read and approved the final manuscript.
TM is on the leave to University of Tsukuba Tandem Accelerator Complex, 1-1-1 Tenno-dai, Tsukuba City, Ibaraki, Japan. MY is on the leave to Nihon Institute of Medical Science, 1276 Shimokawara, Moroyamamachi, Irumagun, Saitama, Japan. YH is on the leave to Robert Research Institute, University of Western Ontario, Canada.
Ethics approval and consent to participate
The retrospective data analysis was approved by the Ethics Committee at the authors’ institution. The radiosynthesis device was approved as a medical device in Japan (22400BZX00441000) on 21 November 2012.
Consent for publication
All participants gave written informed consent before entry into the study.
HI is a patent inventor of the two-hole two-layered face mask and the rapid radiopharmaceutical synthesis/inhalation system. He also received a research grant from JFE, Tokyo, Japan and Molecular Imaging Labo, Suita City, Osaka, Japan. YH is also a patent co-inventor of the two-hole two-layered face mask. All other authors have no conflict of interest to disclose, financial or otherwise.
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