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Author (up) Gimenez-Alventosa, V.; Ballester, F.; Vijande, J.
Title VoxelMages: a general-purpose graphical interface for designing geometries and processing DICOM images for PENELOPE Type Journal Article
Year 2016 Publication Applied Radiation And Isotopes Abbreviated Journal Appl. Radiat. Isot.
Volume 118 Issue Pages 251-257
Keywords 87.53.Bn; 87.53.Jw; 87.55.Qr; 87.55.km; 87.55.K
Abstract The design and construction of geometries for Monte Carlo calculations is an error-prone, time-consuming, and complex step in simulations describing particle interactions and transport in the field of medical physics. The software VoxelMages has been developed to help the user in this task. It allows to design complex geometries and to process DICOM image files for simulations with the general-purpose Monte Carlo code PENELOPE in an easy and straightforward way. VoxelMages also allows to import DICOM-RT structure contour information as delivered by a treatment planning system. Its main characteristics, usage and performance benchmarking are described in detail.
Address [Gimenez-Alventosa, V.; Ballester, F.; Vijande, J.] Univ Valencia, Dept Fis Atom Mol & Nucl, E-46100 Valencia, Spain
Corporate Author Thesis
Publisher Pergamon-Elsevier Science Ltd Place of Publication Editor
Language English Summary Language Original Title
Series Editor Series Title Abbreviated Series Title
Series Volume Series Issue Edition
ISSN 0969-8043 ISBN Medium
Area Expedition Conference
Notes WOS:000390736100039 Approved no
Is ISI yes International Collaboration no
Call Number IFIC @ pastor @ Serial 2904
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Author (up) Molina, F.; Aguilera, P.; Romero-Barrientos, J.; Arellano, H.F.; Agramunt, J.; Medel, J.; Morales, J.R.; Zambra, M.
Title Energy distribution of the neutron flux measurements at the Chilean Reactor RECH-1 using multi-foil neutron activation and the Expectation Maximization unfolding algorithm Type Journal Article
Year 2017 Publication Applied Radiation and Isotopes Abbreviated Journal Appl. Radiat. Isot.
Volume 129 Issue Pages 28-34
Keywords
Abstract We present a methodology to obtain the energy distribution of the neutron flux of an experimental nuclear reactor, using multi-foil activation measurements and the Expectation Maximization unfolding algorithm, which is presented as an alternative to well known unfolding methods such as GRAVEL. Self-shielding flux corrections for energy bin groups were obtained using MCNP6 Monte Carlo simulations. We have made studies at the at the Dry Tube of RECH-1 obtaining fluxes of 1.5(4) x 10(13) cm(-2) s(-1) for the thermal neutron energy region, 1.9(5) x 10(12) cm(-2) s(-1) for the epithermal neutron energy region, and 4.3(11) x 10(11) cm(-2) s(-1) for the fast neutron energy region.
Address
Corporate Author Thesis
Publisher Place of Publication Editor
Language Summary Language Original Title
Series Editor Series Title Abbreviated Series Title
Series Volume Series Issue Edition
ISSN 0969-8043 ISBN Medium
Area Expedition Conference
Notes WOS:000413058200005 Approved no
Is ISI yes International Collaboration yes
Call Number IFIC @ pastor @ Serial 3326
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Author (up) Vijande, J.; Granero, D.; Perez-Calatayud, J.; Ballester, F.
Title Monte Carlo dosimetric study of the medium dose rate CSM40 source Type Journal Article
Year 2013 Publication Applied Radiation and Isotopes Abbreviated Journal Appl. Radiat. Isot.
Volume 82 Issue Pages 283-288
Keywords Brachytherapy; Cs-137 seed; TG-43 based dosimetry; Monte Carlo
Abstract The Cs-137 medium dose rate (MDR) CSM40 source model (Eckert & Ziegler BEBIG, Germany) is in clinical use but no dosimetric dataset has been published. This study aims to obtain dosimetric data for the CSM40 source for its use in clinical practice as required by the American Association of Physicists in Medicine (AAPM) and the European Society for Radiotherapy and Oncology (ESTRO). Penelope2008 and Geant4 Monte Carlo codes were used to characterize this source dosimetrically. It was located in an unbounded water phantom with composition and mass density as recommended by AAPM and ESTRO. Due to the low photon energies of Cs-137, absorbed dose was approximated by collisional kerma. Additional simulations were performed to obtain the air-kerma strength, sic. Mass-energy absorption coefficients in water and air were consistently derived and used to calculate collisional kerma. Results performed with both radiation transport codes showed agreement typically within 0.05%. Dose rate constant, radial dose function and anisotropy function are provided for the CSM40 and compared with published data for other commercially available Cs-137 sources. An uncertainty analysis has been performed. The data provided by this study can be used as input data and verification in the treatment planning systems. (C) 2013 Elsevier Ltd. All rights reserved.
Address [Vijande, J.; Ballester, F.] Univ Valencia, Dept Atom Mol & Nucl Phys, E-46100 Burjassot, Spain, Email: Javier.vijande@uv.es
Corporate Author Thesis
Publisher Pergamon-Elsevier Science Ltd Place of Publication Editor
Language English Summary Language Original Title
Series Editor Series Title Abbreviated Series Title
Series Volume Series Issue Edition
ISSN 0969-8043 ISBN Medium
Area Expedition Conference
Notes WOS:000328804000043 Approved no
Is ISI yes International Collaboration no
Call Number IFIC @ pastor @ Serial 1678
Permanent link to this record