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Nuclear instrumentation

Publié le 28 juin 2021
  • H. Carcreff, L. Salmon, F. Malouch, Recent developments in nuclear heating measurement methods inside the OSIRIS reactor, Nuclear Instruments and Methods in Physics Research Section A 942, 162310 (2019).
  • J.M. Verbeke, O. Petit, O. Litaize, A. Chebboubi, Correlated Production and Analog Transport of Fission Neutrons and Photons using Fission Models FREYA, FIFRELIN and the Monte Carlo Code TRIPOLI-4®, IEEE Transactions on Nuclear Science 65 (9), 2471-2478 (2018).
  • D. Mancusi, A. Bonin, F.X. Hugot, F. Malouch, Advances in Monte-Carlo code TRIPOLI-4's treatment of the electromagnetic cascade, EPJ Web of Conferences 170, 01008 (2018).
  • J.M. Verbeke, O. Petit, O. Litaize, A. Chebboubi, Correlated Production and Analog Transport of Fission Neutrons and Photons using Fission Models FREYA, FIFRELIN and the Monte Carlo Code TRIPOLI-4, Proceedings of ANIMMA 2017, Liège, Belgique, 2017. EPJ Web of Conferences 170, 01019 (2018).
  • O. Petit, C. Jouanne, O. Litaize, O. Serot, A. Chebboubi, Y. Pénéliau, FIFRELIN - TRIPOLI-4 Coupling for Monte Carlo Simulations with a Fission Model. Application to Shielding Calculations, Proceedings of ICRS-13 & RPSD-2016, Paris, France, 2016. EPJ Web of Conferences 153, 06003 (2017).
  • L. Barbot, V. Radulovic, C. Destouches et al., Experimental Validation of A Monte Carlo Based Toolbox for Self-Powered Neutron and Gamma Detector Simulation in the OSIRIS MTR, In Proc. of PHYSOR-2016 (2016).
  • D. Fourmentel, V. Raduloviç, L. Barbot et al., Delayed Gamma Measurements in Different Nuclear Research Reactors Bringing Out the Importance of Their Contribution in Gamma Flux Calculations, IEEE Transactions on Nuclear Science 63 (6), 2875-2879 (2016).
  • J.M. Verbeke, O Petit, Stochastic Analog Neutron Transport with TRIPOLI-4 and FREYA : Bayesian Uncertainty Quantification for Neutron Multiplicity Counting, Nucl. Sci. Eng. 183, 214-228 (2016).
  • L. Barbot, V. Raduloviç, L. Snoj, M. Tarchalski, V. Dewynter-Marty and F. Malouch, Calculation to Experiment Comparison of SPND Signals in Various Nuclear Reactor Environments, 4th International Conference ANIMMA 2015, 20-24 April 2015, Lisbon, Portugal.
  • F. Malouch, F. Lopez, L. Barbot, and D. Foumentel, Calculation of neutron and gamma fluxes in support to the interpretation of measuring devices irradiated in the core periphery of the OSIRIS Material Testing Reactor, 4th International Conference ANIMMA 2015, 20-24 April 2015, Lisbon, Portugal.
  • J.M. Verbeke, O. Petit, TRIPOLI-4 and FREYA for Stochastic Analog Neutron Transport. Application to Neutron Multiplicity Counting, ESARDA Symposium 2015, 37th Annual Meeting, Manchester, UK, 2015.
  • O. Petit, E. Dumonteil, Analog Neutron Transport for Nuclear Instrumentation Applications with the Monte Carlo Code TRIPOLI-4, Nuclear Technology, vol. 192, pp 259-263, 2015.
  • A. Péron, F. Malouch, C. M. Diop, Simulation and Comparison of the Calorimeters Measuring the Nuclear Heating in the OSIRIS Reactor, with the TRIPOLI-4® Monte-Carlo Code, IEEE Transactions on Nuclear Science 62 (3), 1218 - 1225 (2015).
  • O. Petit, E. Dumonteil, Analog Neutron Transport for Nuclear Instrumentation Applications with the Monte Carlo Code TRIPOLI-4, ANS RPSD-2014, 18th Topical Meeting of Radiation Protection & Shielding Division of ANS, Knoxville, USA, 2014.
  • A. Péron, F. Malouch, C. M. Diop, Improvement of Nuclear Heating Evaluation inside the Core of the OSIRIS Material Testing Reactor, ISRD 15 (15th International Symposium on Reactor Dosimetry), 18-23 May 2014, Aix-en-Provence, France.
  • Sari, F. Carrel, C. Jouanne, F. Laineé, A. Lyoussi, O. Petit, Optimization of the Photoneutron Flux emitted by an Electron Accelerator for Neutron Interrogation Applications using MCNP and TRIPOLI-4 Monte Carlo Codes and Performance Assessment on 220 liter Nuclear Waste Mock-up Drums, Proceedings of INMM 54th Annual Meeting, Palm Desert, USA, 2013.
  • Sari, F. Carrel, C. Jouanne, O. Petit, A. Lyoussi, Optimization of the Photoneutron Flux emitted by an Electron Accelerator for Neutron Interrogation Applications using MCNP and TRIPOLI-4 Monte Carlo Codes, Proceedings of IPAC 2013, Shanghai, China, 2013.
  • Y.-K. Lee, J.C. David and H. Carcreff, A Gamma Heating Calculation Methodology for Research Reactor Application, 5th Int. Topical Meeting on Research Reactor Fuel Management, RRFM 2001, Aachen, Germany, p. 147 (2001).
  • ​Y. Péneliau, Electron Photon Shower Simulation TRIPOLI-4 in Monte Carlo Code, Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, Lisbon, Portugal (2000).