External Publication List

2016

  • Experimental Validation of Control Rod Reactivity Worth and Fission Rate Distributions for the CROCUS Reactor Rais A, Hursin M, Perret G, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
  • Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures F, Zwermann W
    ND2013: International Conference on Nuclear Data for Science and Technology 2016, 1 (2016).
  • Nuclear data uncertainty propagation on spent fuel nuclide compositions Leray O, Rochman D, Grimm P, Ferroukhi H, Vasiliev A, Hursin M, Perret G, Pautz A
    ANNALS OF NUCLEAR ENERGY 94, 603-611 (2016).
    DOI: 10.1016/j.anucene.2016.03.023
  • Re-evaluation of the thermal neutron capture cross section of Nd-147 Rochman D, Leray O, Perret G, Vasiliev A, Ferroukhi H, Koning A J
    ANNALS OF NUCLEAR ENERGY 94, 612-617 (2016).
    DOI: 10.1016/j.anucene.2016.03.024
  • Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX Hursin Mathieu, Scriven Michael, Perret Gregory, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 91, 48-58 (2016).
    DOI: 10.1016/j.anucene.2015.12.035
  • Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions Perret G, Blaise P, Messaoudi N, Geslot B, Wagemans J, Baeten P, Kochetkov A, Pautz A
    ANNALS OF NUCLEAR ENERGY 97, 165 (2016).
    DOI: 10.1016/j.anucene.2016.07.015
  • Verification of the New Implementations in SHARK-X for Reactivity Coefficients and Relative Reactivity Worth UQ Hursin M, Siefman D, Perret G, Grimm P, Pautz A
    PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).

2015

  • A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT Aufiero M, Bidaud A, Hursin M, Leppaenen J, Palmiotti G, Pelloni S, Rubiolo P
    ANNALS OF NUCLEAR ENERGY 85, 245 (2015).
    DOI: 10.1016/j.anucene.2015.05.008
  • Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions Hursin M, Downar T, Yoon J, Joo H
    ANNALS OF NUCLEAR ENERGY 87, 356 (2015).
  • Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution Hursin M, Joo H, Downar T
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 3, 2394 (2015).
  • BWR Full Core Analysis with SERPENT/SIMULATE-3 Hybrid Stochastic/Determinstic Code Sequence Hursin M, Rossinelli L, Ferroukhi H, Pautz A
    M&C + SNA + MC 2015: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method 63, 1 (2015).
  • Delayed Neutron Fraction and Prompt Decay Constant Measurement in the MINERVE Reactor using the PSI Instrumentation Perret G
    ANIMMA 2015: Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 20-24 April 2015, Lisbon 1, 1 (2015).
  • Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor Siefman Daniel J, Girardin Gaetan, Rais Adolfo, Pautz Andreas, Hursin Mathieu
    ANNALS OF NUCLEAR ENERGY 85, 434-443 (2015).
    DOI: 10.1016/j.anucene.2015.05.004
  • Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    Science and Technology of Nuclear Installations 2015, 237646 (2015).
    DOI: 10.1155/2015/237646
  • Neutron production and thermal moderation at the PSI UCN source Becker H, Bison G, Blau B, Chowdhuri Z, Eikenberg J, Fertl M, Kirch K, Lauss B, Perret G, Reggiani D, Ries D, Schmidt-Wellenburg P, Talanov V, Wohlmuther M, Zsigmond G
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 777, 20-27 (2015).
    DOI: 10.1016/j.nima.2014.12.091
  • Toward Reanalysis of the Tight-Pitch HCLWR-PROTEUS Phase II Experiments Perret G, Vlassopoulos E, Hursin M, Pautz A
    Wonder 2015: Fourth International Workshop on Nuclear Data Evaluation for Reactor Applications 1, 1 (2015).
  • Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis Hursin Mathieu, Perret Gregory, Pautz Andreas
    ANNALS OF NUCLEAR ENERGY 77, 300-309 (2015).
    DOI: 10.1016/j.anucene.2014.11.019

2014

  • CASMO-4E AND CASMO-5 ANALYSIS OF THE ISOTOPIC COMPOSITIONS OF THE LWR-PROTEUS PHASE II BURNT PWR UO2 FUEL SAMPLES Grimm P, Perret G, Ferroukhi H
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104066 (2014).
  • Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5 Rossinelli L, Hursin M, Ferroukhi H, Pautz A
    ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
  • PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    IGORR: International Group on Research Reactors, 17-21 November 2014, Bariloche, Argentina 1, 1 (2014).
  • PINPOWER UNCERTAINTY QUANTIFICATION OF LWR-PROTEUS PHASE III EXPERIMENTS Hursin M, Scriven M, Perret G, Grimm P, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1099077 (2014).
  • Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools Ferroukhi H, Leray O, Hursin M, Vasiliev A, Perret G, Pautz A
    NUCLEAR DATA SHEETS 118, 498-501 (2014).
    DOI: 10.1016/j.nds.2014.04.117
  • The Development and Implementation of a One-Dimensional S-n Method in the 2D-1D Integral Transport Solution Hursin M, Collins B, Xu Y, Downar T
    NUCLEAR SCIENCE AND ENGINEERING 176, 186-200 (2014).
    DOI: 10.13182/NSE12-4
  • UNCERTAINTY QUANTIFICATION OF SPENT FUEL NUCLIDE COMPOSITIONS DUE TO CROSS SECTIONS, DECAY CONSTANTS AND FISSION YIELDS Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104088 (2014).
  • VALIDATION OF TWO MONTE CARLO CODES FOR LWR BURNUP CALCULATIONS Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
    PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105825 (2014).
  • VERIFICATION OF A REACTOR PHYSICS CALCULATION SCHEME FOR THE CROCUS REACTOR Hursin M, Siefman D, Rais A, Girardin G, Pautz A
    ITMSR-3: 3rd International Technical Meeting on Small Reactors, 5-7 Nov 2015, Ottawa, Canada 1, 1 (2014).

2013

  • ANALYSIS OF PIN REMOVAL EXPERIMENTS CONDUCTED IN A SUPERCRITICAL LIGHT WATER REACTOR-LIKE TEST LATTICE Chewla Rakesh, Raetz Dominik, Jordan Kelly A, Perret Gregory
    NUCLEAR TECHNOLOGY 183, 321-330 (2013).
    DOI: 10.13182/NT13-A19421
  • Comparison of serpent and CASMO-5M for pressurized water reactors models Hursin M, Vasiliev A, Ferroukhi H, Pautz A
    M&C 2013 1, 1565 (2013).
  • Experimental Validation of 3-D Reconstructed Pin Power Distributions in Full-Scale BWR Fuel Assemblies with Partial-Length Rods Giust Flavio Dante, Grimm Peter, Chawla Rakesh
    NUCLEAR SCIENCE AND ENGINEERING 175, 292-307 (2013).
    DOI: 10.13182/NSE12-69
  • Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor Kroehnert H, Perret G, Murphy M F, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 698, 72-80 (2013).
    DOI: 10.1016/j.nima.2012.09.008
  • Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident Hursin Mathieu, Downar Thomas J, Montgomery Robert
    NUCLEAR ENGINEERING AND DESIGN 262, 180-188 (2013).
    DOI: 10.1016/j.nucengdes.2013.04.023
  • Reanalysis of the Gas-cooled fast reactor experiments at the zero power facility Proteus - Spectral indices Perret G, Pattupara R M, Girardin G, Chawla R
    WONDER-2012 - 3RD INTERNATIONAL WORKSHOP ON NUCLEAR DATA EVALUATION FOR REACTOR APPLICATIONS 42, UNSP 05002 (2013).
    DOI: 10.1051/epjconf/20134205002

2012

  • A novel design approach for a neutron measurement station for burnt fuel Dietler Rodolfo, Hursin Mathieu, Perret Gregory, Jordan Kelly, Chawla Rakesh
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 693, 59-66 (2012).
    DOI: 10.1016/j.nima.2012.07.009
  • ANALYSIS OF PIN REMOVAL EXPERIMENTS CONDUCTED IN AN SCWR-LIKE TEST LATTICE Chawla R, Raetz D, Jordan KA, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 283_1 (2012).
  • Analysis of the Core Power Response During a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code Hursin Mathieu, Downar Thomas J, Kochunas Brendan
    NUCLEAR SCIENCE AND ENGINEERING 170, 151-167 (2012).
    DOI: 10.13182/NSE10-75
  • DESIGN OF A PROTEUS LATTICE REPRESENTATIVE OF A BURNT AND FRESH FUEL INTERFACE AT POWER CONDITIONS IN LIGHT WATER REACTORS Hursin M, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 52_1 (2012).
  • EXPERIMENTAL VALIDATION OF CASMO-4E AND CASMO-5M FOR RADIAL FISSION RATE DISTRIBUTIONS IN A WESTINGHOUSE SVEA-96 OPTIMA2 BWR FUEL ASSEMBLY Grimm P, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 50_1 (2012).
  • Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice Raetz Dominik, Jordan Kelly A, Bayard Andre-Samuel P, Perret Gregory, Chawla Rakesh
    NUCLEAR ENGINEERING AND DESIGN 247, 236-247 (2012).
    DOI: 10.1016/j.nucengdes.2012.02.011
  • On the Combination of Delayed Neutron and Delayed Gamma Measurement Techniques for Nuclear Fuel and Its Application to Nuclear Data Uncertainty Reduction Perret Gregory, Jordan Kelly A
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE 59, 3166-3172 (2012).
    DOI: 10.1109/TNS.2012.2215339
  • REANALYSIS OF THE GAS-COOLED FAST REACTOR EXPERIMENTS AT THE ZERO POWER FACILITY PROTEUS – SPECTRAL INDICES Perret G, Pattupara RM, Girardin G, Chawla R
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 176_1 (2012).
  • TOWARDS THE REANALYSIS OF VOID COEFFICIENTS MEASUREMENTS AT PROTEUS FOR HIGH CONVERSION LIGHT WATER REACTOR LATTICES Hursin M, Koeberl O, Perret G
    PHYSOR 2012: Advances in Reactor Physics - Linking Research, Industry, and Education , 53_1 (2012).

2011

  • A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel Jordan K A, Perret G
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 634, 91-100 (2011).
    DOI: 10.1016/j.nima.2011.01.064
  • Comparison of measured and calculated reaction rate distributions in an scwr-like test lattice Raetz Dominik, Jordan Kelly A, Murphy Michael F, Perret Gregory, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 38, 794-801 (2011).
    DOI: 10.1016/j.anucene.2010.11.021
  • Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies Giust Flavio D, Grimm Peter, Chawla Rakesh
    JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME 133, 052909 (2011).
    DOI: 10.1115/1.4002823
  • Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice Raetz Dominik, Jordan Kelly A, Perret Gregory, Chawla Rakesh
    ANNALS OF NUCLEAR ENERGY 38, 2319-2332 (2011).
    DOI: 10.1016/j.anucene.2011.07.007