UB Paderborn / Katalog / Suche / in CDI

Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 2015-04, Vol.780, p.68-80

2015

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Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experiments

Annals of nuclear energy, 2018, Vol.124, p.524-532

2018

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HORUS3D/N Neutron Calculation Tool, a Deterministic Scheme Dedicated to JHR Design and Safety Studies

Nuclear science and engineering, 2018-02, Vol.189 (2), p.188-198

2018

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HORUS3D/N neutron calculation tool, a deterministic scheme dedicated to JHR design and safety studies: development, validation, biases and uncertainties quantification

Nuclear science and engineering, 2018, Vol.189 (2)

2018

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Analysis of the AMMON experimental program in the EOLE facility supporting the qualification of the JHR neutron and photon tools

2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), 2013, p.1-9

2013

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IEEE_Xplore

Design of a Devoted [Formula Omitted] Spectrometry Device for Axial and Azimuthal Activity Measurements on JHR-Type Curved Fuel Plates

IEEE transactions on nuclear science, 2014-08, Vol.61 (4), p.2240

2014

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Design of a devoted γ spectroscopy device for axial and azimuthal activity measurements on JHR-type curved fuel plates

2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), 2013, p.1-6

2013

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IEEE_Xplore

Reactivity Loss Validation of High-Burnup PWR Fuels with Pile-Oscillation Experiments in MINERVE

Nuclear science and engineering, 2013-11, Vol.175 (3), p.308-317

2013

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Monte Carlo Interpretation of the AMMON/REF Experiment in EOLE for the JHR Reactor Neutron Calculations

Nuclear science and engineering, 2013-11, Vol.175 (3), p.318-328

2013

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Nuclear Heating Measurement in Critical Facilities and Experimental Validation of Code and Libraries – An Application to Prompt and Delayed γ Nuclear Data Needs

Physics procedia, 2014, Vol.59, p.3-16

2014

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Neutron Inelastic Scattering Measurements for Na, Ge, Zr, Mo and U

Nuclear data sheets, 2014-05, Vol.119, p.186-189

2014

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The TANDEM Euratom project: Context, objectives and workplan

NUCLEAR DATA UNCERTAINTY QUANTIFICATION FOR THE DECAY HEAT OF PWR MOX FUELS USING DATA ASSIMILATION OF ELEMENTARY FISSION BURSTS

Implementation of probabilistic assessments to support the ASTRID decay heat removal systems design process

Local Neutron Flux Distribution Measurements by Wire-Dosimetry in the AMMON Experimental Program in the EOLE Reactor

First feedback with the AMMON integral experiment for the JHR calculations

Design of a Devoted \gamma Spectrometry Device for Axial and Azimuthal Activity Measurements on JHR-Type Curved Fuel Plates

Analysis of the AMMON Experimental Program in the EOLE Facility Supporting the Qualification of the JHR Neutron and Photon Tools

Monte Carlo Interpretation of the Photon Heating Measurements in the Integral AMMON/REF Experiment in the EOLE Facility

Neutronics Experimental Validation of the Jules Horowitz Reactor Fuel by Interpretation of the VALMONT Experimental Program-Transposition of the Uncertainties on the Reactivity of JHR With JEF2.2 and JEFF3.1.1

Interpretation of PERLE Experiment for the Validation of Iron Nuclear Data Using Monte Carlo Calculations

New 56Fe Covariances for the JEFF3 File from the Feedback of Integral Benchmark Analysis

Needs of Accurate Prompt and Delayed γ-spectrum and Multiplicity for Nuclear Reactor Designs

Analysis of power transients in the CABRI experimental reactor with a multi-physics APOLLO3®/THEDI coupling

Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycle

Experimental validation of photon-heating calculation for the Jules Horowitz Reactor

Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experiments

HORUS3D/N Neutron Calculation Tool, a Deterministic Scheme Dedicated to JHR Design and Safety Studies

HORUS3D/N neutron calculation tool, a deterministic scheme dedicated to JHR design and safety studies: development, validation, biases and uncertainties quantification

Analysis of the AMMON experimental program in the EOLE facility supporting the qualification of the JHR neutron and photon tools

Design of a Devoted [Formula Omitted] Spectrometry Device for Axial and Azimuthal Activity Measurements on JHR-Type Curved Fuel Plates

Design of a devoted γ spectroscopy device for axial and azimuthal activity measurements on JHR-type curved fuel plates

Reactivity Loss Validation of High-Burnup PWR Fuels with Pile-Oscillation Experiments in MINERVE

Monte Carlo Interpretation of the AMMON/REF Experiment in EOLE for the JHR Reactor Neutron Calculations

Nuclear Heating Measurement in Critical Facilities and Experimental Validation of Code and Libraries – An Application to Prompt and Delayed γ Nuclear Data Needs

Neutron Inelastic Scattering Measurements for Na, Ge, Zr, Mo and U

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