[en] The authors present the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in any point of complex industrial installations. They present the current industrial version (PANTHEREV1) and its different applications, and more particularly an investigation in the field of qualification of hardware under irradiation in case of severe accident. They present the currently under development version (PANTHEREV2) which will be exploited in 2011

[en] The authors present the two successive versions of the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in complex industrial installations. This software predicts dose rates and thus enables interventions in irradiating environment to be optimized. The authors report the demonstration of the industrial version (PANTHEREv1) and of the currently under development version (PANTHEREv2). They outline the evolutions brought to the first version to develop the second one such as the direct importation of CAD models, ergonomic improvements, etc.

[en] This document gathers the slides of the available presentations given during these conference days. Twenty seven presentations are assembled in the document and deal with: 1 - GATE: calculation code for medical imaging, radiotherapy and dosimetry (S. Jan); 2 - estimation of conversion factors for the measurement of the ambient dose equivalent rate by in-situ spectroscopy (J.P. Laedermann); 3 - geometry specific calibration factors for nuclear medicine activity meters (F. Bochud); 4 - Monte Carlo simulation of a rare gases measurement system - calculation and validation, ASGA/VGM system (A. Ferragut); 5 - design of a realistic radiation field for the calibration of the dosemeters used in interventional radiology/cardiology (medical personnel dosimetry) (J.M. Bordy); 6 - determination of the position and height of the KALINA facility chimney at CEA Cadarache (L.L. Parisi); 7 - MERCURAD^TM - 3D simulation software for dose rates calculation (R. Abou-Khalil); 8 - PANTHERE - 3D software for gamma dose rates simulation of complex nuclear facilities (M. Longeot); 9 - radioprotection, from the design to the exploitation of radioactive materials transportation containers (S. Kitsos); 10 - post-simulation processing of MCNPX responses in neutron spectroscopy (J.E. Groetz); 11 - last developments of the Geant4 Monte Carlo code for trace amounts simulation in liquid water at the molecular scale (C. Villagrasa); 12 - Calculation of H_p(3)/K_air conversion coefficients using PENELOPE Monte-Carlo code and comparison with MCNP calculation results (J. Daures); 13 - artificial neural networks, a new alternative to Monte Carlo calculations for radiotherapy (E. Martin); 14 - use of case-based reasoning for the reconstruction and handling of voxelized fantoms (J. Henriet); 15 - resolution of the radioactive decay inverse problem for dose calculation in radioprotection (A. Tsilanizara); 16 - use of NURBS-type fantoms for the study of the morphological factors influencing the pulmonary anthropo-radiometry (J. Farah); 17 - evaluation of the GUINEVERE experiment shielding (W. Uyttenhove); 18 - GATE/GEANT4 validation for external radiotherapy (Y. Perrot); 19 - European intercomparison of Monte Carlo code users for the kerma uncertainty calculation in air near a ¹³⁷Cs source (L. De Carlan); 20 - decision threshold and detection limit in gamma dose rate measurement (A. Vivier); 21 - uncertainties spreading from basic data of nuclear reactors key parameters (I. Kodeli); 22 - evaluation of secondary neutrons-related doses received by patients treated by proton-therapy (R. Sayah); 23 - radioprotection optimization for nuclear medicine patients: doses evaluation for the new reference voxelized fantoms of the CIPR (international commission of radiological protection) (L. Hadid); 24 - radiological accident reconstruction using numerical tools: towards a more and more realistic representation of the victim (E. Courageot); 25 - new tools for treatment optimization after internal contamination by Pu/Am/Cm (P. Fritsch); 26 - development of an expert system for the consideration of uncertainties in internal contamination monitoring (E. Davesne); 27 - CUTADOSE, a calculation code for skin dose estimation after skin contamination (X. Michel). (J.S.)