CV Accueil - Archive ouverte HAL

	Comparison of Direct and Adjoint k and α-Eigenfunctions Vito Vitali , Florent Chevallier , Alexis Jinaphanh , Andrea Zoia , Patrick Blaise Journal of Nuclear Engineering, 2021, 2 (2), pp.132-151. ⟨10.3390/jne2020014⟩ Article dans une revue hal-04427819v1
	Neutron heating assessment in Minerve reactor by using alanine/ESR dosimetry F. Rouihem , W. Dridi , M. Daoudi , Patrick Blaise , B. Geslot Annals of Nuclear Energy, 2020, 142, pp.107456. ⟨10.1016/j.anucene.2020.107456⟩ Article dans une revue cea-02524689v1
	Collective dipole effects in ionic transport under electric fields N. Salles , L. Martin-Samos , S. de Gironcoli , L. Giacomazzi , M. Valant Nature Communications, 2020, 11, pp.3330. ⟨10.1038/s41467-020-17173-w⟩ Article dans une revue hal-02888925v1
	Attenuation of neutron and photon-induced irradiation damage in pressurized water reactor pressure vessels Shengli Chen , David Bernard , Patrick Blaise Annals of Nuclear Energy, 2020, 145, pp.107601 -. ⟨10.1016/j.anucene.2020.107601⟩ Article dans une revue hal-03490649v1
	Interpretation of the ASPIS Iron 88 programme with TRIPOLI-4® and quantification of uncertainties due to nuclear data Amine Hajji , Christine Coquelet-Pascal , Patrick Blaise Annals of Nuclear Energy, 2020, 140, pp.107147. ⟨10.1016/j.anucene.2019.107147⟩ Article dans une revue cea-02534748v1
	Spectral analysis by direct and adjoint Monte Carlo methods Vito Vitali , Florent Chevallier , Alexis Jinaphanh , Patrick Blaise , Andrea Zoia Annals of Nuclear Energy, 2020, 137, pp.107033. ⟨10.1016/j.anucene.2019.107033⟩ Article dans une revue hal-03488748v1
	Transient Fission Matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations Patrick Blaise , Axel Laureau , Paul Ros , Pierre Leconte , Kornilios Routsonis Annals of Nuclear Energy, 2019, 128, pp.390-397. ⟨10.1016/j.anucene.2019.01.031⟩ Article dans une revue cea-02510825v1
	Extension of Bayesian inference for multi-experimental and coupled problem in neutronics − a revisit of the theoretical approach Thomas Frosio , Thomas Bonaccorsi , Patrick Blaise EPJ N - Nuclear Sciences & Technologies, 2018, 4, pp.19. ⟨10.1051/epjn/2018046⟩ Article dans une revue cea-02305474v1
	Tests and foreseen developments of fibered-OSLD gamma-heating measurements in low-power reactors A. Gruel , M. Le Guillou , Patrick Blaise , C. Destouches , Sylvain Magne IEEE Transactions on Nuclear Science, 2018, 65 (9), pp.2490 - 2493. ⟨10.1109/TNS.2018.2827393⟩ Article dans une revue cea-01917204v1
	Modeling of the $^3$He Density Evolution Inside the CABRI Transient Rods During Power Transients Olivier Clamens , Johann Lecerf , Jean-Pascal Hudelot , Bertrand Duc , Patrick Blaise IEEE Transactions on Nuclear Science, 2018, 65 (9), pp.2510-2517. ⟨10.1109/tns.2018.2818928⟩ Article dans une revue cea-02429990v1
	Modeling Representative Gen-IV Molten Fuel Reactivity Effects in the ZEPHYR ZPR. Part II LFR Analysis Marat Margulis , Patrick Blaise , Erez Gilad International Journal of Energy Research, 2018, 43 (2), pp.829-843. ⟨10.1002/er.4313⟩ Article dans une revue cea-02340010v1
	Optimization of CABRI power transients with the SPARTE code and the URANIE uncertainty platform O. Clamens , J.-P. Hudelot , Patrick Blaise , J. Lecerf , B. Duc Annals of Nuclear Energy, 2018, 119, pp.271-278. ⟨10.1016/j.anucene.2018.05.025⟩ Article dans une revue cea-02339832v1
	Application of the EGPT methodology in the analysis of small-sample reactivity worth experiments Pierre Leconte , Jean Tommasi , Alain Santamarina , Patrick Blaise , Paul Ros EPJ N - Nuclear Sciences & Technologies, 2018, 4, pp.44. ⟨10.1051/epjn/2018041⟩ Article dans une revue cea-02304319v1
	Coupled Experimental and Computational Approach for CABRI Power Transients Analysis Olivier Clamens , Patrick Blaise , Jean-Pascal Hudelot , Johann Lecerf , Bertrand Duc IEEE Transactions on Nuclear Science, 2018, 65 (9), pp.2434-2442. ⟨10.1109/tns.2018.2847331⟩ Article dans une revue hal-02429520v1
	Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2 Gilles Noguere , Bernard David , Patrick Blaise , Olivier Bouland , Luiz C. Leal Nuclear Science and Engineering, 2017, 182 (2), pp.135-150. ⟨10.13182/NSE15-9⟩ Article dans une revue cea-02386210v1
	State of the art on nuclear heating measurement methods and expected improvements in zero power research reactors Mael Le Guillou , Adrien Gruel , Christophe Destouches , Patrick Blaise EPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.11. ⟨10.1051/epjn/2017002⟩ Article dans une revue cea-02305885v1
	Impact of correlations between core configurations for the evaluation of nuclear data uncertainty propagation for reactivity Thomas Frosio , Patrick Blaise , Thomas Bonaccorsi EPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.6. ⟨10.1051/epjn/2016039⟩ Article dans une revue cea-02381386v1
	Artificial neural network surrogate development of equivalence models for nuclear data uncertainty propagation in scenario studies Guillaume Krivtchik , Patrick Blaise , Christine Coquelet-Pascal EPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.22. ⟨10.1051/epjn/2017012⟩ Article dans une revue cea-02304906v1
	Fast-thermal coupled cores in zero power reactors: A demonstration of feasibility and pertinence for the ZEPHYR project P. Ros , P. Leconte , Patrick Blaise , Hugo Doger de Spéville , Maxence Maillot Annals of Nuclear Energy, 2017, 110, pp.290-305. ⟨10.1016/j.anucene.2017.06.019⟩ Article dans une revue cea-02421904v1
	The path for innovative severe accident neutronics studies in ZPRs. Part I.2: Interpretation of SNEAK-12A experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients M. Margulis , Patrick Blaise , Frederic Mellier , Erez Gilad Progress in Nuclear Energy, 2017, 96, pp.97-117. ⟨10.1016/j.pnucene.2016.12.006⟩ Article dans une revue cea-02389231v1
	The path for innovative severe accident neutronics studies in ZPRs - Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs M. Margulis , Patrick Blaise , Fabrizio Gabrielli , Adrien Gruel , Frederic Mellier Progress in Nuclear Energy, 2017, 94, pp.106-125. ⟨10.1016/j.pnucene.2016.11.001⟩ Article dans une revue cea-02389252v1
	Theoretical insights and experimental characterization of HfO 2 -based OxRRAMs operation Boubacar Traore , Patrick Blaise , E. Vianello , B. Sklenard Journal of Computational Electronics, 2017, 16 (4), pp.1045-1056. ⟨10.1007/s10825-017-1085-5⟩ Article dans une revue hal-01671617v1
	Validation of Monte-Carlo Methods for Generation Time and Delayed Neutron Fraction Predictions Gregory Perret , Nadia Messaoudi , Patrick Blaise , Benoit Geslot , Jan Wagemans Annals of Nuclear Energy, 2016, 97, pp.165-170. ⟨10.1016/j.anucene.2016.07.015⟩ Article dans une revue cea-02389803v1
	Nuclear data uncertainties propagation methods in Boltzmann/Bateman coupled problems: Application to reactivity in MTR Thomas Frosio , Thomas Bonaccorsi , Patrick Blaise Annals of Nuclear Energy, 2016, 90, pp.303-317. ⟨10.1016/j.anucene.2015.12.010⟩ Article dans une revue cea-02381443v1
	Surrogates based multi-criteria predesign methodology of Sodium-cooled Fast Reactor cores - Application to CFV-like cores Olivier Fabbris , Saied Dardour , Patrick Blaise , Jean-Henry Ferrasse , Manuel Saez Nuclear Engineering and Design, 2016, 305, pp.314-333. ⟨10.1016/j.nucengdes.2016.05.021⟩ Article dans une revue hal-01461795v1

	Tests and foreseen developments of fibered-OSLD gamma heating measurements in low-power reactors A. Gruel , M. Le Guillou , Patrick Blaise , C. Destouches , Sylvain Magne ANIMMA 2017 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications, Jun 2017, Liège, Belgium. pp.04010, ⟨10.1051/epjconf/201817004010⟩ Communication dans un congrès cea-01772739v1
	The CANDELLE experiment for characterization of neutron sensitivity of LiF TLDs M.Le Guillou , A. Billebaud , A. Gruel , G. Kessedjian , O. Meplan International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA 2017), Jun 2017, Liège, Belgium. pp.04014, ⟨10.1051/epjconf/201817004014⟩ Communication dans un congrès in2p3-01685106v1
	Experimental R and D innovation for Gen-II,III et IV neutronics studies in ZPRs : a path to the future ZEPHYR facility in Cadarache P. Blaise , F. Boussard , P. Ros , P. Leconte , M. Margulis RRFM/IGORR 2016 - European Research Reactor Conference (IGORR) - International Group Operating Research Reactor (IGORR), Mar 2016, Berlin, Germany Communication dans un congrès cea-02442364v1
	Neutron activation of natural materials in a PWR spectrum: Feedback on 116mIn relative γ emission intensities and half-life Adrien Gruel , Benoit Geslot , Jacques Di Salvo , Patrick Blaise , Jean-Michel Girard 2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Apr 2015, Lisbon, Portugal. pp.1-5, ⟨10.1109/ANIMMA.2015.7465599⟩ Communication dans un congrès cea-03181119v1
	Integral ($n$,$\gamma$) Cross-sections Measurement of Standard Light Water Reactors Materials A. Gruel , B. Geslot , A. Pepino , J Di Salvo , P. Leconte IGORR 2014 - 16th Meeting of the International Group on Research Reactors, Nov 2014, San Carlos de Bariloche, Argentina Communication dans un congrès cea-02874693v1
	FLUOLE-2: An Experiment for PWR Pressure Vessel Surveillance N. Thiollay , J. Di Salvo , C. Sandrin , M. Soldevila , S. Bourganel 15th International Symposium on Reactor Dosimetry (ISRD 15), May 2014, Aix en Provence, France. pp.02015, ⟨10.1051/epjconf/201610602015⟩ Communication dans un congrès in2p3-01283891v1

	Reactor Physics Experiments on Zero Power Reactors G. Bignan , Philippe Fougeras , Patrick Blaise , Jean-Pascal Hudelot , Frédéric Mellier Handbook of Nuclear Engineering, Springer US, pp.2053-2184, 2010, ⟨10.1007/978-0-387-98149-9_18⟩ Chapitre d'ouvrage cea-02071309v1

	Representativity studies of PROTEUS UO$_2$ fuel for new GEN-III+-type configurations in the EOLE Critical Facility Patrick Blaise , Mathieu Hursin , Adrien Gruel , Gregory Perret 2020 Pré-publication, Document de travail cea-02480922v1

Patrick BLAISE

Publications

Comparison of Direct and Adjoint k and α-Eigenfunctions

Neutron heating assessment in Minerve reactor by using alanine/ESR dosimetry

Collective dipole effects in ionic transport under electric fields

Attenuation of neutron and photon-induced irradiation damage in pressurized water reactor pressure vessels

Interpretation of the ASPIS Iron 88 programme with TRIPOLI-4® and quantification of uncertainties due to nuclear data

Spectral analysis by direct and adjoint Monte Carlo methods

Transient Fission Matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations

Extension of Bayesian inference for multi-experimental and coupled problem in neutronics − a revisit of the theoretical approach

Tests and foreseen developments of fibered-OSLD gamma-heating measurements in low-power reactors

Modeling of the $^3$He Density Evolution Inside the CABRI Transient Rods During Power Transients

Modeling Representative Gen-IV Molten Fuel Reactivity Effects in the ZEPHYR ZPR. Part II LFR Analysis

Optimization of CABRI power transients with the SPARTE code and the URANIE uncertainty platform

Application of the EGPT methodology in the analysis of small-sample reactivity worth experiments

Coupled Experimental and Computational Approach for CABRI Power Transients Analysis

Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

State of the art on nuclear heating measurement methods and expected improvements in zero power research reactors

Impact of correlations between core configurations for the evaluation of nuclear data uncertainty propagation for reactivity

Artificial neural network surrogate development of equivalence models for nuclear data uncertainty propagation in scenario studies

Fast-thermal coupled cores in zero power reactors: A demonstration of feasibility and pertinence for the ZEPHYR project

The path for innovative severe accident neutronics studies in ZPRs. Part I.2: Interpretation of SNEAK-12A experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients

The path for innovative severe accident neutronics studies in ZPRs - Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs

Theoretical insights and experimental characterization of HfO 2 -based OxRRAMs operation

Validation of Monte-Carlo Methods for Generation Time and Delayed Neutron Fraction Predictions

Nuclear data uncertainties propagation methods in Boltzmann/Bateman coupled problems: Application to reactivity in MTR

Surrogates based multi-criteria predesign methodology of Sodium-cooled Fast Reactor cores - Application to CFV-like cores

Tests and foreseen developments of fibered-OSLD gamma heating measurements in low-power reactors

The CANDELLE experiment for characterization of neutron sensitivity of LiF TLDs

Experimental R and D innovation for Gen-II,III et IV neutronics studies in ZPRs : a path to the future ZEPHYR facility in Cadarache

Neutron activation of natural materials in a PWR spectrum: Feedback on 116mIn relative γ emission intensities and half-life

Integral ($n$,$\gamma$) Cross-sections Measurement of Standard Light Water Reactors Materials

FLUOLE-2: An Experiment for PWR Pressure Vessel Surveillance

Reactor Physics Experiments on Zero Power Reactors

Representativity studies of PROTEUS UO$_2$ fuel for new GEN-III+-type configurations in the EOLE Critical Facility