Shielding calculation for the Proton-Therapy-Center in Prague, Czech Republic (original) (raw)
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IPAC 2014 - A proton therapy test facility the radiation protection design
A proton therapy test facility with a beam current lower than 10 nA in average, and an energy up to 85 MeV, has to be sited at The accelerator is composed by a sequence of linear sections. From the radiation protection point of view the source of radiation for this facility is almost completely located at the final target. Physical and geometrical models of the device have been developed and implemented into a radiation transport computer code based on Monte Carlo method. The main scope is the assessment of the dose rates around the radiation source for supporting the safety analysis. For the assessment was used the FLUKA (FLUktuierende KAskade) computer code. A general purpose tool for the calculation of particle transport and interaction with matter, covering an extended range of applications including proton beam analysis. The models implemented into the code are described and the results are presented. The calculated dose rates are reported at different distances from the target. Considerations about personnel safety are issued and the shielding requirements are anticipated.
Shielding study at the Fukui Prefectural Hospital Proton Therapy Center
Journal of Nuclear Science and Technology, 2012
At the Fukui Prefectural Hospital Proton Therapy Center, neutron doses behind the concrete shields and at the maze were measured with three types of radiation monitors (DARWIN, Wendi-2, and a rem meter) along with solid-state nuclear track detectors. The measured data were compared with estimations of analytical models and the Monte Carlo code, Particle and Heavy-Ion Transport code System (PHITS). The analytical model, using the parameters employed in the shielding design of the facility, gave considerably larger values than the measured data. This means that the facility was designed with a sufficient margin of safety. The results calculated by PHITS were less than those of the analytical model and were about three times larger than the measured data. From a perspective that seeks conservative estimation with less margin, the Monte Carlo simulation is a good tool for shielding design of accelerator-based proton treatment facilities.
A PROTON THERAPY TEST FACILITY: THE RADIATION PROTECTION DESIGN
A proton therapy test facility is planned to be sited in the Frascati ENEA Research Center, in Italy. A 30 m long, 3 m wide bunker has to be designed to host a proton linear accelerator with a low beam current, lower than 10 nA in average, and an energy up to 150 MeV. The accelerator will be part of the TOP-IMPLART project for deep tumors treatment. The design of the 150 MeV accelerator is under study and the radiation protection solutions are considered in this phase. The linear accelerator has some safety advantages if compared to cyclotrons and synchrotrons. It can be easily housed in the long, narrow tunnel. The main radiation losses during the acceleration process occur below 20 MeV, with a low neutron production. As a consequence the barriers needed should be substantially lighter than the one used for other types of machines. In the paper the simulation models and the calculation performed with Monte Carlo codes are described. The related results are presented together with t...
Technical Physics
Proton therapy is an effective method of treating oncologic diseases. In Russia, construction of several centers for proton and ion therapy is slated for the years to come. A proton therapy center in Dimitrovgrad will be the first. The Joint Institute for Nuclear Research (Russia) in collaboration with Ion Beam Application (IBA) (Belgium) has designed an C235-V3 medical proton cyclotron for this center. It outperforms previous versions of commercial IBA cyclotrons, which have already been installed in 11 oncologic hospital centers in different countries. Experimental and calculation data for the beam dynamics in the C235-V3 medical cyclotron are presented. Reasons for beam losses during acceleration are considered, the influence of the magnetic field radial component in the midplane of the accelerator and main resonances is studied, and a beam extraction system is designed. In 2011–2012 in Dubna, the cyclotron was mounted, its magnetic field was properly configured, acceleration con...
Radiation safety issues relevant to proton therapy and radioisotope production medical cyclotrons
Radiation Protection and Environment, 2012
Medical cyclotrons are now constructed as turnkey facilities at nuclear medicine clinics, specialised particle therapy facilities and radioisotope production centres. Most medical cyclotrons usually accelerate protons to high energies and could be divided mainly in two categories: (a) Low energy (E P = 15-30 MeV) machines, dedicated for medical positron emission tomography and single photon emission computer tomography radioisotope production and (b) High energy (E P = 100-250 MeV) machines, predominantly used for radiotherapy of malignant tumours. Parasitic gamma and neutron radiation are produced during the operation of medical cyclotrons. Furthermore, high level of gamma radiation produced by the activated cyclotron components could impose radiation exposure to maintenance crew. Hence, radiation safety is imperative to safe and reliable operation of medical cyclotron facilities. A sound operational health physics procedure assures the minimisation of radiation exposure to patients and members of the public abiding the regulatory guidelines. This paper highlights the important radiation safety aspects related to safe operation of proton therapy and radioisotope production medical cyclotrons.
Operational health physics during the commissioning phase of West German proton therapy centre Essen
The West German Proton Therapy Centre Essen (Westdeutsches Protonentherapiezentrum Essen) also called WPE is one of the most advanced particle therapy centres in Western Europe and now undergoing its commissioning phase. The first patient treatment is planned to take place in the third quarter of 2012. The WPE operates a 230 MeV proton cyclotron, delivering proton beams of energies varying from 80 to 225 MeV to four treatment rooms. Unexpected radiation exposures to medical physicists and technicians conducting important validation tests in the treatment rooms are the main concerns during commissioning runs of our facility. We have investigated the radiation exposure from the leakage radiations through treatment room and labyrinth walls as well as activated beam apertures, beamshaping compensators, and various types of polystyrene plate-and water tank phantoms. Specific dose reduction techniques have been developed and implemented within the framework of operational health physics during the commissioning of the WPE.
Neutron field analysis for a proton therapy installation
A proton therapy centre is planned to be sited in Rome, Italy. It will be based on a medium energy proton accelerator and should be associated to a National Health Institute. At least two treatment station should be realized: a 140 MeV area for shallow tumors therapy and the 200-250 MeV full energy station for deep tumors treatment. Additional experimental areas are foresee for studying the interactions of low energy, high LET, protons with tissues and the effectiveness of proton therapy on specific pathologies. The project is now in a preliminary design phase. The accelerator is under study, the building layout has to be defined and the preliminary safety solutions are considered as well in this phase. The radiation protection approach requires that all the radiation fields are well known, even those that are not useful for the treatment itself. In this frame the neutron field due to proton interactions in solid, liquid and gaseous materials has to be analyzed during the design pha...
Applied Radiation and Isotopes, 2020
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Radiation safety and operational health physics of hospital based medical cyclotrons
2002
Compact, low energy, high current Medical Cyclotrons are now primarily used to produce large activities of short lived, neutron deficient, positron-emitting radioisotopes, 11 C [E(β +) = 385 keV av , T 1/2 = 20.4 min], 13 N [E(β +) = 491 keV av , T 1/2 = 9.7 min], 15 O [E(β +) = 735 keV av , T 1/2 = 2.3 min] and 18 F [E(β +) = 242 keV av , T 1/2 = 110 min]. These isotopes constitute the key ingredients of important PET (Positron Emission Tomography) radiopharmaceuticals used in diagnostic nuclear medicine. The PET-radioisotope producing Medical Cyclotrons are now increasingly installed in modern urban hospitals in many countries of the world. Modern Medical Cyclotrons run at a very high beam current (~200 micro Amp) level and thereby produce intense fields of parasitic gamma rays and neutrons, causing the activation of cyclotron components, ambient air and radiation exposure to patients and members of the public. This report highlights the important operational aspects and the characteristics of the radiation fields produced by Medical Cyclotrons. The pathways of personnel radiation exposure are also analyzed. The above information constitutes the scientific basis of a sound operational health physics service, which is manifested in an effective dose reduction and an enhanced radiological safety of the Medical Cyclotron facility within the framework of ALARA principle.
Nukleonika, 2016
This work presents recombination methods used for secondary radiation measurements at the Facility for Proton Radiotherapy of Eye Cancer at the Institute for Nuclear Physics, IFJ, in Krakow (Poland). The measurements of H*(10) were performed, with REM-2 tissue equivalent chamber in two halls of cyclotrons AIC-144 and Proteus C-235 and in the corridors close to treatment rooms. The measurements were completed by determination of gamma radiation component, using a hydrogen-free recombination chamber. The results were compared with the measurements using rem meter types FHT 762 (WENDI-II) and NM2 FHT 192 gamma probe and with stationary dosimetric system.