Patrick BLAISE
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Tests and foreseen developments of fibered-OSLD gamma-heating measurements in low-power reactorsIEEE Transactions on Nuclear Science, 2018, 65 (9), pp.2490 - 2493. ⟨10.1109/TNS.2018.2827393⟩
Article dans une revue
cea-01917204v1
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State of the art on nuclear heating measurement methods and expected improvements in zero power research reactorsEPJ N - Nuclear Sciences & Technologies, 2017, 3, pp.11. ⟨10.1051/epjn/2017002⟩
Article dans une revue
cea-02305885v1
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The path for innovative severe accident neutronics studies in ZPRs - Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRsProgress in Nuclear Energy, 2017, 94, pp.106-125. ⟨10.1016/j.pnucene.2016.11.001⟩
Article dans une revue
cea-02389252v1
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Tests and foreseen developments of fibered-OSLD gamma heating measurements in low-power reactorsANIMMA 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
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The CANDELLE experiment for characterization of neutron sensitivity of LiF TLDsInternational 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
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Neutron activation of natural materials in a PWR spectrum: Feedback on 116mIn relative γ emission intensities and half-life2015 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
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Integral ($n$,$\gamma$) Cross-sections Measurement of Standard Light Water Reactors MaterialsIGORR 2014 - 16th Meeting of the International Group on Research Reactors, Nov 2014, San Carlos de Bariloche, Argentina
Communication dans un congrès
cea-02874693v1
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FLUOLE-2: An Experiment for PWR Pressure Vessel Surveillance15th 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
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Representativity studies of PROTEUS UO$_2$ fuel for new GEN-III+-type configurations in the EOLE Critical Facility2020
Pré-publication, Document de travail
cea-02480922v1
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