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Beam port filters in a TRIGA MARK III nuclear reactor to produce epithermal neutrons for BNCT. Appl Radiat Isot 2021; 179:110018. [PMID: 34749092 DOI: 10.1016/j.apradiso.2021.110018] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/07/2021] [Revised: 10/27/2021] [Accepted: 11/02/2021] [Indexed: 01/15/2023]
Abstract
Glioblastoma multiforme is the most common and aggressive brain tumor and it is difficult to treat with conventional surgery, chemotherapy, or radiation therapy. An alternative treatment is boron neutron capture therapy which requires an energy modulated beam of neutrons and a10B drug capable of adhering to the tumor. In this work, MCNP6 Monte Carlo code was used to evaluate the effect on the neutron spectrum by placing two filters along the radial beam tube of the TRIGA Mark III nuclear reactor of ININ in Mexico. Every filter was made with the same amount and type of materials: Steel and Graphite for filter 1 and Cadmium, Aluminum, and Cadmium (Cd + Al + Cd) for filter 2. Two cases were analyzed for each filter as follows: Case A for filter 1 was considering 30 cm of steel and 30 cm of graphite, while for case B, the dimensions of filter 1 were 15 cm of steel, 15 cm of graphite, 15 cm of steel and 15 cm of graphite. Cases A and B for filter 2 were analyzed considering the same dimensions and amount of materials. The work was in the aim to produce epithermal neutrons for boron neutron capture therapy. Neutron spectra were calculated at three sites along the beam tube and two sites outside the beam tube; here, the ambient dose equivalent, the personal dose equivalent, and the effective doses were also estimated. At a distance of 517 cm of core, in case B, results in an epithermal-to-thermal neutron fluence ratio of 30.39 was obtained being larger than the one recommended by the IAEA of 20.
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Ziegner M, Schmitz T, Khan R, Blaickner M, Palmans H, Sharpe P, Hampel G, Böck H. Confirmation of a realistic reactor model for BNCT dosimetry at the TRIGA Mainz. Med Phys 2015; 41:111706. [PMID: 25370620 DOI: 10.1118/1.4897242] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
PURPOSE In order to build up a reliable dose monitoring system for boron neutron capture therapy (BNCT) applications at the TRIGA reactor in Mainz, a computer model for the entire reactor was established, simulating the radiation field by means of the Monte Carlo method. The impact of different source definition techniques was compared and the model was validated by experimental fluence and dose determinations. METHODS The depletion calculation code origen2 was used to compute the burn-up and relevant material composition of each burned fuel element from the day of first reactor operation to its current core. The material composition of the current core was used in a mcnp5 model of the initial core developed earlier. To perform calculations for the region outside the reactor core, the model was expanded to include the thermal column and compared with the previously established attila model. Subsequently, the computational model is simplified in order to reduce the calculation time. Both simulation models are validated by experiments with different setups using alanine dosimetry and gold activation measurements with two different types of phantoms. RESULTS The mcnp5 simulated neutron spectrum and source strength are found to be in good agreement with the previous attila model whereas the photon production is much lower. Both mcnp5 simulation models predict all experimental dose values with an accuracy of about 5%. The simulations reveal that a Teflon environment favorably reduces the gamma dose component as compared to a polymethyl methacrylate phantom. CONCLUSIONS A computer model for BNCT dosimetry was established, allowing the prediction of dosimetric quantities without further calibration and within a reasonable computation time for clinical applications. The good agreement between the mcnp5 simulations and experiments demonstrates that the attila model overestimates the gamma dose contribution. The detailed model can be used for the planning of structural modifications in the thermal column irradiation channel or the use of different irradiation sites than the thermal column, e.g., the beam tubes.
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Affiliation(s)
- Markus Ziegner
- AIT Austrian Institute of Technology GmbH, Vienna A-1220, Austria and Institute of Atomic and Subatomic Physics, Vienna University of Technology, Vienna A-1020, Austria
| | - Tobias Schmitz
- Institut für Kernchemie, Johannes Gutenberg-Universität, Mainz DE-55128, Germany
| | - Rustam Khan
- Pakistan Institute of Engineering and Applied Sciences (PIEAS), Islamabad PK-44000, Pakistan
| | | | - Hugo Palmans
- Acoustics and Ionising Radiation Division, National Physical Laboratory, Teddington TW11 0LW, United Kingdom and Medical Physics Group, EBG MedAustron GmbH, Wiener Neustadt A-2700, Austria
| | - Peter Sharpe
- Acoustics and Ionising Radiation Division, National Physical Laboratory, Teddington TW11 0LW, United Kingdom
| | - Gabriele Hampel
- Institut für Kernchemie, Johannes Gutenberg-Universität, Mainz DE-55128, Germany
| | - Helmuth Böck
- Institute of Atomic and Subatomic Physics, Vienna University of Technology, Vienna A-1020, Austria
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Akan Z, Türkmen M, Çakir T, Reyhancan İA, Çolak Ü, Okka M, Kiziltaş S. Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications. Appl Radiat Isot 2015; 99:110-6. [PMID: 25746919 DOI: 10.1016/j.apradiso.2015.02.014] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 02/14/2014] [Revised: 10/18/2014] [Accepted: 02/18/2015] [Indexed: 11/25/2022]
Abstract
This paper aims to describe the modification of the radial beam port of ITU (İstanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented.
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Affiliation(s)
- Zafer Akan
- Department of Biophysics, School of Medicine, Celal Bayar University, Manisa, Turkey
| | - Mehmet Türkmen
- Department of Nuclear Engineering, Hacettepe University, Beytepe Campus, Ankara, Turkey.
| | - Tahir Çakir
- Department of Radiation Oncology, School of Medicine, Yüzüncü Yıl University, Van, Turkey
| | - İskender A Reyhancan
- Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey
| | - Üner Çolak
- Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey
| | - Muhittin Okka
- Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey
| | - Sahip Kiziltaş
- Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey
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Žerovnik G, Kaiba T, Radulović V, Jazbec A, Rupnik S, Barbot L, Fourmentel D, Snoj L. Validation of the neutron and gamma fields in the JSI TRIGA reactor using in-core fission and ionization chambers. Appl Radiat Isot 2014; 96:27-35. [PMID: 25479432 DOI: 10.1016/j.apradiso.2014.10.026] [Citation(s) in RCA: 23] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/11/2014] [Revised: 10/24/2014] [Accepted: 10/30/2014] [Indexed: 10/24/2022]
Abstract
CEA developed fission chambers and ionization chambers were utilized at the JSI TRIGA reactor to measure neutron and gamma fields. The measured axial fission rate distributions in the reactor core are generally in good agreement with the calculated values using the Monte Carlo model of the reactor thus verifying both the computational model and the fission chambers. In future, multiple absolutely calibrated fission chambers could be used for more accurate online reactor thermal power monitoring.
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Affiliation(s)
- Gašper Žerovnik
- Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia; Faculty of Mathematics and Physics, University of Ljubljana, Jadranska ulica 19, SI-1000 Ljubljana, Slovenia.
| | - Tanja Kaiba
- Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia.
| | - Vladimir Radulović
- Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia; CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance, France.
| | - Anže Jazbec
- Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia.
| | - Sebastjan Rupnik
- Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia.
| | - Loïc Barbot
- CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance, France.
| | - Damien Fourmentel
- CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance, France.
| | - Luka Snoj
- Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia.
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Computational analysis of irradiation facilities at the JSI TRIGA reactor. Appl Radiat Isot 2012; 70:483-8. [PMID: 22154389 DOI: 10.1016/j.apradiso.2011.11.042] [Citation(s) in RCA: 37] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/15/2011] [Revised: 11/01/2011] [Accepted: 11/18/2011] [Indexed: 11/23/2022]
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Blaickner M, Kratz JV, Minouchehr S, Otto G, Schmidberger H, Schütz C, Vogtländer L, Wortmann B, Hampel G. Dosimetric feasibility study for an extracorporeal BNCT application on liver metastases at the TRIGA Mainz. Appl Radiat Isot 2011; 70:139-43. [PMID: 21872481 DOI: 10.1016/j.apradiso.2011.08.008] [Citation(s) in RCA: 10] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 08/05/2010] [Revised: 08/05/2011] [Accepted: 08/06/2011] [Indexed: 12/01/2022]
Abstract
This study investigates the dosimetric feasibility of Boron Neutron Capture Therapy (BNCT) of explanted livers in the thermal column of the research reactor in Mainz. The Monte Carlo code MCNP5 is used to calculate the biologically weighted dose for different ratios of the (10)B-concentration in tumour to normal liver tissue. The simulation results show that dosimetric goals are only partially met. To guarantee effective BNCT treatment the organ has to be better shielded from all gamma radiation.
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Affiliation(s)
- M Blaickner
- Health & Environment Department-Molecular Medicine, AIT Austrian Institute of Technology GmbH, Muthgasse 11, A-1190 Vienna, Austria.
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Abstract
Neutron capture therapy (NCT) is a form of radiation therapy using nuclides having a high propensity for capturing thermal neutrons and reacting with a prompt nuclear reaction (i.e. disintegration). If these nuclides are introduced selectively into tumor cells it is theoretically possible to destroy the tumor and to spare the surrounding normal tissue. The principles of this modality were described in 1936. First clinical trials in the USA from 1951 to 1961 using 10B resulted in failure. Since 1968 patients suffering from glioblastoma have been successfully treated in Japan by NCT with 10B and since 1987 another Japanese group has treated melanoma using NCT. The Japanese experiences and recent advances in the evaluation of tumor-affinitive boron-containing drugs have spurred interest in NCT. This article presents some basic physical notions and a historic overview of NCT that emphasizes the well documented early trials as well as some recent developments. Problems which occurred in the past now demand special efforts for a better understanding of the effects of NCT before starting new clinical trials in the next few years.
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