Full External Publication List

2019

  • Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario Paranjape S, Mignot G, Kapulla R, Paladino D
    NUCLEAR ENGINEERING AND DESIGN 342, 88 (2019).
    DOI: 10.1016/j.nucengdes.2018.11.017
  • Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
    RADIATION PHYSICS AND CHEMISTRY 156, 292 (2019).
    DOI: 10.1016/j.radphyschem.2018.11.017

2018

  • Large Scale Experiments Representing a Containment Natural Circulation Loop during an Accident Scenario Kapulla R, Mignot G, Paranjape S, Andreani M, Paladino D
    Science and Technology of Nuclear Installations 2018, 1 (2018).
    DOI: 10.1155/2018/8989070
  • PIV measurements in the vicinity of a steam sparger in the PANDA facility Kapulla R, Uong D, Zimmer C, Paladino D
    NUCLEAR ENGINEERING AND DESIGN 336, 112 (2018).
    DOI: 10.1016/j.nucengdes.2017.07.003

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

2010

  • Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel Krohnert H, Perret G, Murphy M F, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 624, 101-108 (2010).
    DOI: 10.1016/j.nima.2010.09.033

2009

  • Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography Caruso S, Murphy M F, Jatuff F, Chawla R
    NUCLEAR ENGINEERING AND DESIGN 239, 1220-1228 (2009).
    DOI: 10.1016/j.nucengdes.2009.02.019
  • Experimental Validation of Reaction Rate Distributions for a SVEA-96+BWR Assembly with Hafnium Control Blades Plaschy Michael, Murphy Michael, Jatuff Fabian, Luethi Anton, Grimm Peter, Jacot-Guillarmod Roland, Giust Flavio, Bergmann Uffe, Helmersson Sture, Seiler Rudolf, Krouthen Jan, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 46, 933-943 (2009).
    DOI: 10.1080/18811248.2009.9711602
  • Impact of New Gadolinium Cross Sections on Reaction Rate Distributions in 10 x 10 BWR Assemblies Perret G, Murphy M F, Jatuff F, Sublet J-Ch, Bouland O, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 163, 17-25 (2009).
    DOI: 10.13182/NSE08-55
  • Void reactivity coefficient benchmark results for a 10 x 10 BWR assembly in the full 0-100% void fraction range Jatuff F, Perret G, Murphy M F, Giust F, Chawla R
    ANNALS OF NUCLEAR ENERGY 36, 853-858 (2009).
    DOI: 10.1016/j.anucene.2009.02.013

2008

  • Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optimal assembly Perret G, Plaschy M, Murphy M F, Jatuff F, Chawla R
    ANNALS OF NUCLEAR ENERGY 35, 478-484 (2008).
    DOI: 10.1016/j.anucene.2007.06.025
  • Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions Murphy M F, Jatuff F, Perret G, Plaschy M, Bergmann U, Chawla R
    ANNALS OF NUCLEAR ENERGY 35, 2042-2050 (2008).
    DOI: 10.1016/j.anucene.2008.06.001
  • Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of (CS)-C-134 Cs-137 and Eu-154 single ratios inhighly burnt UO2 Caruso S, Guenther-Leopold I, Murphy M F, Jatuff F, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 589, 425-435 (2008).
    DOI: 10.1016/j.nima.2008.03.005
  • Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+test lattice Chawla R, Jatuff F, Tani F
    ANNALS OF NUCLEAR ENERGY 35, 495-502 (2008).
    DOI: 10.1016/j.anucene.2007.06.027
  • Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography Caruso Stefano, Murphy Michael F, Jatuff Fabian, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 45, 828-835 (2008).
    DOI: 10.3327/jnst.45.828

2007

  • Radial and azimuthal U-235 fission and U-238 capture distributions in BWR UO2 pins: CASMO-4 and MCNP4C versus activation foil measurements Macku K, Jatuff F, Murphy M, Plaschy M, Grimm P, Joneja O P, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 155, 96-101 (2007).
  • Validation of Cs-134, Cs-137 and Eu-154 single ratios as burnup monitors for ultra-high burnup UO2 fuel Caruso S, Murphy M, Jatuff F, Chawla R
    ANNALS OF NUCLEAR ENERGY 34, 28-35 (2007).
    DOI: 10.1016/j.anucene.2006.11.009

2006

  • A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor Paratte J M, Frueh R, Kasemeyer U, Kalugin M A, Timm W, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 739-748 (2006).
    DOI: 10.1016/j.anucene.2005.09.012
  • Absolute depth-dose-rate measurements for an Ir-192 HDR brachytherapy source in water using MOSFET detectors Zilio Valery Olivier, Joneja Om Parkash, Popowski Youri, Rosenfeld Anatoly, Chawla Rakesh
    MEDICAL PHYSICS 33, 1532-1539 (2006).
    DOI: 10.1118/1.2198168
  • Advanced foil activation techniques for the measurement of within-pin distributions of the Cu-63(n,gamma)Cu-64 reaction rate in nuclear fuel Macku K, Jatuff F, Murphy MF, Joneja OP, Bischofberger R, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 562, 393-400 (2006).
    DOI: 10.1016/j.nima.2006.03.004
  • Calibration of MOSFET detectors for absolute dosimetry with an (IR)-I-192 HDR brachytherapy source Zilio V, Joneja O, Popowski Y, Rosenfeld A, Chawla R
    STRAHLENTHERAPIE UND ONKOLOGIE 182, 175-175 (2006).
  • Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades Plaschy Michael, Jatuff Fabian, Grimm Peter, Tani Filippo, Jacot-Guillarmod Roland, Giust Flavio, Krouthen Jan, Chawla Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43, 1298-1310 (2006).
    DOI: 10.3327/jnst.43.1298
  • Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10X10 BWR assembly Jatuff F, Giust F, Krouthen J, Helmersson S, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 119-125 (2006).
    DOI: 10.1016/j.anucene.2005.09.007
  • Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, Chawla R
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43, 223-230 (2006).
    DOI: 10.3327/jnst.43.223
  • HTGR reactor physics and fuel cycle studies Kuijper JC, Raepsaet X, de Haas JBM, von Lensa W, Ohlig U, Ruetten HJ, Brockmann H, Damian F, Dolci F, Bernnat W, Oppe J, Kloosterman JL, Cerullo N, Lomonaco G, Negrini A, Magill J, Seiler R
    NUCLEAR ENGINEERING AND DESIGN 236, 615-634 (2006).
    DOI: 10.1016/j.nucengdes.2005.10.021
  • On the accuracy of reactor physics calculations for square HPLWR fuel assemblies Jatuff F, Macku K, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 198-207 (2006).
    DOI: 10.1016/j.anucene.2005.09.006
  • Optimised non-invasive method to determine U-238-captures-to-total-fissions in reactor fuel Bergmann UC, Chawla R, Jatuff F, Murphy MF
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 556, 331-338 (2006).
    DOI: 10.1016/j.nima.2005.08.110
  • Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples Murphy M F, Jatuff F, Grimm P, Seiler R, Brogli R, Meier G, Berger H-D, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 760-765 (2006).
    DOI: 10.1016/j.anucene.2006.04.003
  • Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+BWR assembly Tani F, Jatuff F, Chawla R
    ANNALS OF NUCLEAR ENERGY 33, 490-498 (2006).
    DOI: 10.1016/j.anucene.2006.02.005

2005

  • (CE)-C-144 as a potential candidate for interstitial and intravascular brachytherapy Zilio VO, Joneja OP, Popowski Y, Bochud FO, Chawla R
    INTERNATIONAL JOURNAL OF RADIATION ONCOLOGY BIOLOGY PHYSICS 62, 585-594 (2005).
    DOI: 10.1016/j.ijrobp.2005.02.005
  • A polynomial form for higher-order accurate quantification of perturbation effects in nuclear systems van Geemert R, Tani F
    NUCLEAR SCIENCE AND ENGINEERING 149, 74-87 (2005).
    DOI: 10.13182/NSE05-A2478
  • Within-pin reaction rate distributions: CASMO-4 and HELIOS compared against tomographic measurements at the PROTEUS reactor Fauchere CP, Murphy M, Jatuff F, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 150, 27-36 (2005).
    DOI: 10.13182/NSE05-A2499

2004

  • Adapting and applying SPECT to the investigation of reaction rate distributions within lightly activated nuclear fuel pins Fauchere CP, Jatuff F, Murphy M, Chawla R
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 522, 579-590 (2004).
    DOI: 10.1016/j.nima.2003.12.001
  • Development and application of a decomposition methodology for interpretation of reactivity effect discrepancies van Geemert R, Jatuff F, Tani F, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 148, 162-171 (2004).
    DOI: 10.13182/NSE04-A2448
  • Experimental determination of the ratio of U-238 capture to U-235 fission in LEU-HTR pebble-bed configurations Koberl O, Seiler R, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 146, 1-12 (2004).
  • Plutonium management in the medium term Hesketh K, Schlosser G, Porsch DF, Wolf T, Koberl O, Lance B, Chawla R, Gehin JC, Ellis R, Uchikawa S, Sato O, Okubo T, Mineo H, Yamamoto T, Sagayama Y, Sartori E
    NUCLEAR TECHNOLOGY 148, 244-258 (2004).
    DOI: 10.13182/NT04-A3564
  • Quantification of the transferability of reactivity effect investigations in large multiregion systems van Geemert R, Jatuff F, Tani F, Chawla R
    ANNALS OF NUCLEAR ENERGY 31, 1735-1763 (2004).
    DOI: 10.1016/j.anucene.2004.05.001

2003

  • Comparison of various partial light water reactor core loadings with inert matrix and mixed-oxide fuel Kasemeyer U, Hellwig C, Lebenhaft J, Chawla R
    JOURNAL OF NUCLEAR MATERIALS 319, 142-153 (2003).
    DOI: 10.1016/S0022-3115(03)00146-6
  • Interpretation of experimental results from moderate-power in-pile testing of a Pu-Er-Zr-oxide inert matrix fuel Hellwig C, Kasemeyer U, Ledergerber G, Lee BH, Lee YW, Chawla R
    ANNALS OF NUCLEAR ENERGY 30, 287-299 (2003).
    DOI: 10.1016/S0306-4549(02)00059-2
  • Measurement and interpretation of delayed photoneutron effects in multizone criticals with partial D2O moderation Jatuff F, Luthi A, Murphy M, Williams T, Chawla R
    ANNALS OF NUCLEAR ENERGY 30, 1731-1755 (2003).
    DOI: 10.1016/S0306-4549(03)00136-1
  • Validation of axial pin power distributions in a 10 x 10 BWR assembly across an enrichment boundary under full-density water moderation conditions Jatuff F, Grimm P, van Geemert R, Murphy M, Seiler R, Brogli R, Giust F, Jacot-Guillarmod R, Williams T, Helmersson S, Chawla R
    ANNALS OF NUCLEAR ENERGY 30, 911-930 (2003).
    DOI: 10.1016/S0306-4549(02)00144-5

2002

  • Assessment of reactivity effects due to localized perturbations in BWR lattices van Geemert R, Jatuff F, Grimm R, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 142, 96-106 (2002).
    DOI: 10.13182/NSE02-A2291
  • Feasibility of partial LWR core loadings with inert-matrix fuel Kasemeyer U, Hellwig C, Dean DW, Chawla R, Meier G, Williams T
    ADVANCED REACTORS WITH INNOVATIVE FUELS, WORKSHOP PROCEEDINGS , 245-260 (2002).
  • Neutronics investigations for the lower part of a westinghouse SVEA-96+assembly Murphy MF, Luthi A, Seiler R, Grimm P, Joneja O, Meister A, van Geemert R, Jatuff F, Brogli R, Jacot-Guillarmod R, Williams T, Helmersson S, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 141, 32-45 (2002).
    DOI: 10.13182/NSE02-A2264

2001

  • Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice Chawla R, Grimm P, Heimgartner P, Jatuff F, Ledergerber G, Luthi A, Murphy M, Seiler R, van Geemert R
    PROGRESS IN NUCLEAR ENERGY 38, 359-362 (2001).
    DOI: 10.1016/S0149-1970(00)00135-9
  • LWR-PROTEUS verification of reaction rate distributions in modern 10 x 10 boiling water reactor fuel Jatuff F, Grimm R, Joneja O, Murphy M, Luthi A, Seiler R, Brogli R, Jacot-Guillarmod R, Williams T, Helmersson S, Chawla R
    NUCLEAR SCIENCE AND ENGINEERING 139, 262-272 (2001).
    DOI: 10.13182/NSE01-A2236
  • Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries Joneja OP, Plaschy M, Jatuff F, Luthi A, Murphy M, Seiler R, Chawla R
    ANNALS OF NUCLEAR ENERGY 28, 701-713 (2001).
    DOI: 10.1016/S0306-4549(00)00079-7

2000

  • Epithermal inverse kinetic measurements and their interpretation using a two-group point-kinetic model Rosselet M, Chawla R, Williams T
    NUCLEAR SCIENCE AND ENGINEERING 135, 33-47 (2000).
    DOI: 10.13182/NSE99-33

1999

  • A high-fluence 0.6 GeV proton irradiation experiment with thin uranium and thorium targets Wenger HU, Botta F, Chawla R, Gavillet D, Kopajtic Z, Ledergerber G, Linder H, Rollin S
    ANNALS OF NUCLEAR ENERGY 26, 141-148 (1999).
    DOI: 10.1016/S0306-4549(98)89001-4
  • Conceptual studies for pressurised water reactor cores employing plutonium-erbium-zirconium oxide inert matrix fuel assemblies Stanculescu A, Kasemeyer U, Paratte JM, Chawla R
    JOURNAL OF NUCLEAR MATERIALS 274, 146-152 (1999).
    DOI: 10.1016/S0022-3115(99)00082-3
  • Investigation of the k(eff)-variation upon water ingress in a pebble-bed LEU-HTR Rosselet M, Chawla R, Williams T
    ANNALS OF NUCLEAR ENERGY 26, 75-82 (1999).
    DOI: 10.1016/S0306-4549(98)80001-7
  • Time-dependent boundary source term for advanced nodal diffusion theory Jatuff FE, Gho CJ
    ANNALS OF NUCLEAR ENERGY 26, 1065-1082 (1999).
    DOI: 10.1016/S0306-4549(98)00102-9
  • Validation efforts for the neutronics of a plutonium-erbium-zirconium oxide inert matrix light water reactor fuel Paratte JM, Chawla R, Fruh R, Joneja OP, Pelloni S, Pralong C
    JOURNAL OF NUCLEAR MATERIALS 274, 120-126 (1999).
    DOI: 10.1016/S0022-3115(99)00086-0

1998

  • Impact of methods and data on calculational results for LWR lattices employing uranium-free plutonium fuels Pelloni S, Kasemeyer U, Paratte JM, Chawla R
    KERNTECHNIK 63, 239-248 (1998).

1997

  • Planning calculations for new LWR experiments at the PROTEUS facility Ziver A, Brogli R, Chawla R, Grimm P, Hager H, Seiler R, Williams T
    JAHRESTAGUNG KERNTECHNIK '97 , 19-22 (1997).
  • Void coefficient analysis of an LWR lattice experiment with high-enrichment MOX fuel Bohme R, Berger HD, Chawla R, Hager H, Seiler R, Williams T
    NUCLEAR ENGINEERING AND DESIGN 168, 271-279 (1997).
    DOI: 10.1016/S0029-5493(96)00002-7

1995

  • ON THE PHYSICS FEASIBILITY OF LWR PLUTONIUM FUELS WITHOUT URANIUM PARATTE JM, CHAWLA R
    ANNALS OF NUCLEAR ENERGY 22, 471-481 (1995).
    DOI: 10.1016/0306-4549(94)00061-I

1992

  • ANALYSIS OF PROTEUS PHASE-II EXPERIMENTS IN SUPPORT OF LIGHT WATER HIGH CONVERSION REACTOR DESIGN CHAWLA R, BOHME R, ALFONSO J, AXMANN J, BERGER HD, HAGER H, PELLONI S, SEILER R, WILLIAMS T
    KERNTECHNIK 57, 14-22 (1992).

1991

  • LEU-HTR CRITICAL EXPERIMENT PROGRAM FOR THE PROTEUS FACILITY IN SWITZERLAND BROGLI R, BUCHER KH, CHAWLA R, FOSKOLOS K, LUCHSINGER H, MATHEWS D, SARLOS G, SEILER R
    ENERGY 16, 507-519 (1991).
    DOI: 10.1016/0360-5442(91)90130-E