¹⁸FDG Synthesis and Supply: a Journey from Existing Centralized to Future Decentralized Models

uz Zaman, Maseeh,Fatima, Nosheen,Sajjad, Zafar,Zaman, Unaiza,Tahseen, Rabia,Zaman, Areeba Asian Pacific Journal of Cancer Prevention 2014 Asian Pacific journal of cancer prevention Vol.15 No.23

Positron emission tomography (PET) as the functional component of current hybrid imaging (like PET/CT or PET/MRI) seems to dominate the horizon of medical imaging in coming decades. $^{18}$Flourodeoxyglucose ($^{18}FDG$) is the most commonly used probe in oncology and also in cardiology and neurology around the globe. However, the major capital cost and exorbitant running expenditure of low to medium energy cyclotrons (about 20 MeV) and radiochemistry units are the seminal reasons of low number of cyclotrons but mushroom growth pattern of PET scanners. This fact and longer half-life of $^{18}F$ (110 minutes) have paved the path of a centralized model in which $^{18}FDG$ is produced by commercial PET radiopharmacies and the finished product (multi-dose vial with tungsten shielding) is dispensed to customers having only PET scanners. This indeed reduced the cost but has limitations of dependence upon timely arrival of daily shipments as delay caused by any reason results in cancellation or rescheduling of the PET procedures. In recent years, industry and academia have taken a step forward by producing low energy, table top cyclotrons with compact and automated radiochemistry units (Lab-on-Chip). This decentralized strategy enables the users to produce on-demand doses of PET probe themselves at reasonably low cost using an automated and user-friendly technology. This technological development would indeed provide a real impetus to the availability of complete set up of PET based molecular imaging at an affordable cost to the developing countries.

사이클로트론 구성부품별 고장통계분석

조준호,정재은,정홍문,원도연,Cho, June-Ho,Jung, Jae-Eun,Jung, Hong-Moon,Won, Do-Yeon 대한디지털의료영상학회 2014 대한디지털의료영상학회논문지 Vol.16 No.1

The demand of cyclotron for PET (positron emission tomography) has rapidly grown as the more use of PET or PET-CT equipment requires the increased amount of radioactive isotopes for clinical positron emission. While research on failure statistics of medical equipment used in medical centers has continued to be done, the analysis and study on failure statistics of cyclotron have rarely been conducted. However, the growing demand shows the urgency of systematical management guideline and countermeasures for device failure to minimize any supply delay of radiopharmaceuticals occurred by such failure and complains from waiting patients for PET-CT diagnosis. Therefore, this study aims to analyze the failure report from Minitrace equipped in cyclotron which is owned by the department of nuclear medicine at Yeungnam University Medical Center and draws on the data to build effective management system for cyclotron.

GEANT4 몬테카를로 전산모사를 이용한 PET 사이클로트론 기반 중성자 선원의 BNCT 적용가능성 평가

최재원,강보선 한국물리학회 2017 New Physics: Sae Mulli Vol.67 No.11

본 연구는 붕소-중성자 포획치료용 (boron neutron capture therapy, BNCT) 중성자 선원으로 사이클로트론의 활용가능성 평가를 위한 선행 연구이다. GEANT4 전산모사 도구를 이용하여 사이클로트론에서 가속된 양성자 빔을 베릴륨 표적에 조사할 때 발생되는 중성자 수율을 계산하였다. 또한 양성자 빔의 에너지와 표적의 두께 변화에 따른 중성자 스펙트럼의 변화와 각도별 수율을 계산하였다. 계산된 결과를 종합하여 중성자 반사체가 포함된 표적의 주요 설계인자를 결정하였고, 설계된 표적에서 발생되는 고열중성자 선속을 계산하였다. 20 MeV 이하의 저에너지 양성자 빔을 조사할 때 발생되는 고열중성자 선속은 BNCT 중성자 선원으로 적합하지 않았으며, 30 MeV 500 $\mu$A 양성자 빔에 의해 발생되는 고열중성자 선속은 1.03$\times$10$^{9}$ n/cm$^{2}$$\cdot$s로서 BNCT 중성자 선원에 요구되는 권고선속 이상의 고열중성자 선속을 발생시킴을 확인하였다. This report presents the results of a feasibility study on a cyclotron-based neutron source for boron neutron-capture therapy (BNCT). Neutron yields from a beryllium target bombarded by a proton beam accelerated by a cyclotron were calculated using the GEANT4 simulation tool kit. The calculations were performed with different proton energies and different target thicknesses to find the changes in neutron spectra and yield at various angles. The main parameters for the design of a target with a neutron reflector were determined based on the calculated results, and epithermal neutron fluxes generated from the target were calculated. The epithermal neutron flux generated by a proton beam with an energy lower than 20 MeV was not sufficient for BNCT. However the flux generated by a 30 MeV, 500 $\mu$A proton beam was 1.03$\times$10$^{9}$ n/cm$^{2}$$\cdot$s, which satisfies the flux recommandation for a BNCT neutron source.

Evaluation of 18F Radioactive Concentration in Exhaust at Cyclotron Facility at Chosun University

정철기,장한,이경진 (사)한국방사선산업학회 2016 방사선산업학회지 Vol.10 No.1

The recent prevalence of PET examinations in Korea has led to an increase in thenumber of cyclotrons. The medical isotope 18F produced in most cyclotron facilities currentlyoperating in Korea is emitted into the environment during the production of [18F]FDG, a cancerdiagnosisreagent. The amount of [18F]FDG synthesized determines the radioactive concentrationof 18F in the exhaust. At some facilities, this amount temporarily exceeds the emission limit. In thisstudy, we evaluated the 18F radioactivity concentration in the exhaust from the cyclotron facilityat Chosun University. The 18F radioactivity concentration was measured using an air sampler anda HPGe semiconductor detector. The measurements showed that the radioactive concentration of18F in the exhaust at the cyclotron facility at Chosun University was the highest during [18F]FDGsynthesis but remained under the legal limit of 2,000 Bq m-3.

Design Study of a 9 MeV Compact Cyclotron System for PET

이병노,신승욱,송호승,김현욱,채종서 한국물리학회 2013 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.62 No.11

A cyclotron is an accelerator which can be applied to both cancer diagnosis and treatment. Among commercially sold cyclotrons, the major energy is used for positron emission tomography (PET) ranges from 10 to 20 MeV. In this research, 9 MeV compact cyclotron for PET was designed. The research was conducted on the response cross section and the yield for the energy distribution to decide the design features. Also, it was determined the specifications on the basis of the fluorodeoxy-glucose (FDG) maximum dose. The machine, which has a 20 uA beam current, is designed to be installed in small-to-medium-sized hospitals in local cities because of its relatively light weight (6tons). This compact cyclotron, which provides 9-MeV proton beams, is composed of a azimuthally varying field (AVF) electromagnet, 83-MHz RF systems with a 20 kW amplifier, a panning ion gauge (PIG) type ion-source for negative hydrogen, and a double-stage high-vacuum system. The basic model design was done by using 3-D CAD program, CATIA and all the field calculations were performed using commercial electromagnetic field analysis code, OPERA-3D TOSCA. From this research, we expect a time reduction for FDG production, a decrease of radioactive exposure for workers, and an equipment cost reduction.

The Distribution of Thermal Neutron Fluxes into the Self-Shielded Wall Equipped with a Medical Self-Shielded PET (Positron Emission Tomography) Cyclotron

M. Sakama,T. Saze,K. Maeda,K. Akamatsu,E. Honda,H. Nishitani 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23

The role of systematic evaluations of thermal neutron fluxes originated in various medical small radiation accelerator facilities has become more and more important to establish uniformly a clearance system about radioactivities of radioactive waste materials produced, for example, when those facilities would be decommissioned and improved. The purpose of this paper was to investigate the distribution of thermal neutron fluxes into the self-shielded wall at the PET cyclotron in Tokushima University Hospital.The distribution of thermal neutron fluxes was determined using the activation Au foil method of ¹⁹⁷Au(n,γ)¹⁹⁸Au reaction and the visualization was observed using the imaging plate (IP) of a long ribbon shaped activation Au thin foil. It was found that the thermal neutron fluxes were distributed from 6.65 × 10^6 cm^(-2) s^(-1) (at 1.5 cm distance from an inside wall into a polyethylene layer) to 1.20 × 10^2 cm^(-2) s^(-1) (at 71.0 cm distance into a heavy concrete layer), and also that the distribution trend of thermal neutron fluxes will be approximately consistent with that of the calculated data led by MCNP code. We have confirmed that it will be possible for the IP visualization of thermal neutron fluxes into the self-shielded wall at the PET cyclotron to reproduce those distribution quantitatively and over a wide area.

Radiological Aspects of PET Cyclotrons operating in Korea

Leila Mokhtari Oranj,Nam-Suk Jung,Arim Lee,Hee-Seock Lee 대한방사선방어학회 2019 대한방사선방어학회 학술발표회 논문요약집 Vol.2019 No.04

KOTRON-13과 상용 PET 사이클로트론의 최근 기술 동향

채종서 ( Jong Seo Chai ) 대한핵의학회 2005 핵의학 분자영상 Vol.39 No.1

Benchmarking of neutron production yields from an H2 18O target in a PET cyclotron with Monte Carlo codes

Mahdi Bakhtiari,Leila Mokhtari Oranj,Nam-Suk Jung,Hee-Seock Lee 대한방사선방어학회 2020 대한방사선방어학회 학술발표회 논문요약집 Vol.2020 No.11

Zr-89 Labeled PAMAM Dendrimers 5G without a Chelator for a Cancer Diagnostic Agent

Lee Jin Hee,Kim Gun Gyun,Kim Sang Wook,Park Joo-Hee 한국물리학회 2020 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.77 No.5

Dendrimer nanoparticles (DNPs), which have been studied extensively as drug delivery systems, can be synthesized easily with zirconium without chelators. A UV/Vis spectrophotometer and a Dynamic Light Scattering (DLS) analysis were used to confirm the synthesis and the particle size of the composite. Compound B synthesized using a chelator compound was found to be more complex than compound A, and natZr was found to bind at a low yield through Scanning Electron Microscopy-Energy Dispersive X-ray Spectrometer (SEM-EDS) and Inductively Coupled Plasma-Mass Spectrometer (ICP-MS). In PBS (1×), The binding was confirmed to be strong and stable at 99% stability or more. The stability to human serum was very good with a value of about 98%. The stability of the bound 89Zr was confirmed to be stable for 160 minutes through the evaluation of serum stability. Using CT-26 and MDA-MB-231, We also were able to confirm the difference in the cell uptake of 89Zr-DNPs. After 24 hours, a high cell uptake of close to 40% was observed. Positron Emission Tomography (PET) images were observed, it was confirmed that no accumulation of 89Zr-DNPs in the bones and its stability in the body.