2018
-
Analysis of Major Group Structures Used for Nuclear Reactor Simulations
International Conference on Nuclear Engineering, Proceedings -, - (2018).DOI: 10.1115/ICONE26-81445
-
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
ANNALS OF NUCLEAR ENERGY 111, 141-151 (2018).DOI: 10.1016/j.anucene.2017.08.061
-
Cross-observables and cross-isotopes correlations in nuclear data from integral constraints
EPJ Nuclear Sciences & Technologies 4, 35 (2018).DOI: 10.1051/epjn/2018011
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Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology
ANNALS OF NUCLEAR ENERGY 342, 323 (2018).DOI: 10.1016/j.anucene.2018.01.037
-
ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library
NUCLEAR DATA SHEETS 142, 1 (2018).DOI: 10.1016/j.nds.2018.02.001
-
Efficient use of Monte Carlo: the fast correlation coefficient
EPJ Nuclear Sciences & Technologies 4, 15 (2018).DOI: 10.1051/epjn/2018019
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Iron NRT- and arc-displacement cross sections and their covariances
Nuclear Materials and Energy 15, 244 (2018).DOI: 10.1016/j.nme.2018.05.006
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Large Scale Experiments Representing a Containment Natural Circulation Loop during an Accident Scenario
Science and Technology of Nuclear Installations 2018, 1 (2018).DOI: 10.1155/2018/8989070
-
Magnetism and the phase diagram of MnSb2O6
PHYSICAL REVIEW B 97, 224416 (2018).DOI: 10.1103/PhysRevB.97.224416
-
Modelling and Analysis of selected OECD PKL3 Station-Blackout Experiments using TRACE
Nuclear Engineering and Technology 1, 1-25 (2018).DOI: 10.1016/j.net.2017.12.005
-
Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA
NUCLEAR ENGINEERING AND DESIGN 328, 36 (2018).DOI: 10.1016/j.nucengdes.2017.12.028
-
Monte Carlo nuclear data adjustment via integral information
The European Physical Journal Plus 133, 537 (2018).DOI: 10.1140/epjp/i2018-12361-x
-
Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
NUCLEAR ENGINEERING AND DESIGN 126, 118 (2018).DOI: 10.1016/j.nucengdes.2018.03.033
-
Nuclear data correlation between different isotopes via integral information
EPJ Nuclear Sciences & Technologies 4, 7 (2018).DOI: 10.1051/epjn/2018006
-
On the characteristics of the flow and heat transfer in the core bypass region
NUCLEAR ENGINEERING AND DESIGN 128, 117 (2018).DOI: 10.1016/j.nucengdes.2018.01.039
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PIV measurements in the vicinity of a steam sparger in the PANDA facility
NUCLEAR ENGINEERING AND DESIGN 336, 112 (2018).DOI: 10.1016/j.nucengdes.2017.07.003
-
Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
ANNALS OF NUCLEAR ENERGY 121, 361 (2018).DOI: 10.1016/j.anucene.2018.07.043
-
SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
PROGRESS IN NUCLEAR ENERGY 283, 278 (2018).DOI: 10.1016/j.pnucene.2018.03.016
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Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor
International Conference on Nuclear Engineering, Proceedings -, - (2018).DOI: 10.1115/ICONE26-81082
-
Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
The European Physical Journal Plus 133, 429 (2018).DOI: 10.1140/epjp/i2018-12303-8
-
Subchannel modeling of single rod bowing in a bundle geometry
NUCLEAR ENGINEERING AND DESIGN 340, 347 (2018).DOI: 10.1016/j.nucengdes.2018.09.032
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Systematics of Nd cumulative fission yields for neutron-induced fission of 235U, 238U, 238Pu, 239Pu, 240Pu and 241Pu
The European Physical Journal Plus 133, 99 (2018).DOI: 10.1140/epjp/i2018-11926-y
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Technical note: On modelling central void formation in LWR fuel pellets due to high-temperature restructuring
Nuclear Engineering and Technology , S1738573318303887 (2018).DOI: 10.1016/j.net.2018.07.003
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Testing of a sCVD diamond detection system in the CROCUS reactor
EUROPEAN PHYSICAL JOURNAL A 54, 82 (2018).DOI: 10.1140/epja/i2018-12519-1
-
Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
EPJ Nuclear Sciences & Technologies 4, 6 (2018).DOI: 10.1051/epjn/2018005
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Unsteady Single-Phase Natural-Circulation Flow Mixing Prediction Using 3-D Thermal-Hydraulic System and CFD Codes
NUCLEAR TECHNOLOGY , 1 (2018).DOI: 10.1080/00295450.2018.1461517
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Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
ANNALS OF NUCLEAR ENERGY 184, 178 (2018).DOI: 10.1016/j.anucene.2018.04.022
2017
-
A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses
ANNALS OF NUCLEAR ENERGY 105, 121-132 (2017).DOI: 10.1016/j.anucene.2017.03.008
-
Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
ANNALS OF NUCLEAR ENERGY 102, 190-199 (2017).DOI: 10.1016/j.anucene.2016.12.015
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Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
PROGRESS IN NUCLEAR ENERGY , 1 (2017).DOI: 10.1016/j.pnucene.2017.03.018
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Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
ANNALS OF NUCLEAR ENERGY 101, 262-269 (2017).DOI: 10.1016/j.anucene.2016.11.025
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Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
ANNALS OF NUCLEAR ENERGY 110, 1023-1029 (2017).DOI: 10.1016/j.anucene.2017.08.022
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Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
M&C 2017 International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P286, 1 (2017).
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Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics
EPJ Web of Conferences 146, 02008 (2017).DOI: 10.1051/epjconf/201714602008
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Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances
PROGRESS IN NUCLEAR ENERGY 96, 76-96 (2017).DOI: 10.1016/j.pnucene.2016.11.006
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Correlation nu-sigma-chi in the fast neutron range via integral information
EPJ Web of Conferences 3, 14 (2017).DOI: 10.1051/epjn/2017009
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Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
ANNALS OF NUCLEAR ENERGY 101, 559-575 (2017).DOI: 10.1016/j.anucene.2016.11.001
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Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor
ANNALS OF NUCLEAR ENERGY 101, 419-428 (2017).DOI: 10.1016/j.pnucene.2017.03.018
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IAEA Neutronics Benchmark for EBR-II SHRT-45R
FR17: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development CN245, 070 (2017).
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Improving Activation Cross Sections for Fusion Applications
FUSION SCIENCE AND TECHNOLOGY 73, 13 (2017).DOI: 10.1080/15361055.2017.1372682
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Kinetic Parameter Measurements in the MINERVE Reactor
IEEE TRANSACTIONS ON NUCLEAR SCIENCE 64, 724 (2017).DOI: 10.1109/TNS.2016.2637569
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Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
ANNALS OF NUCLEAR ENERGY 110, 547-559 (2017).DOI: 10.1016/j.anucene.2017.07.006
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Monte Carlo simulation of scintillation detector for spent fuel characterization in a hot cell
ANS Student Conference 2017, April 6-9, 2017, Pittsburgh, PA, USA , (2017).
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NEW INSIGHTS IN THE FUEL GRAIN SUBDIVISION DURING IN-PLANT IRRADIATION UP TO HIGH BURN-UP
2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea -, - (2017).
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Nodal and Pin-by-pin Calculations Comparison with Codes SIMULATE-5 and DYN3D
M&C 2017: International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P010, 1 (2017).
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Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
NUCLEAR DATA SHEETS 139, 1-76 (2017).DOI: 10.1016/j.nds.2017.01.001
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Nuclear Data Uncertainty Decomposition for SPERT-III RIA Experiments using SIMULATE-3K and SHARK-X
M&C 2017: International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P236, 1 (2017).
-
Post-Dryout Heat Transfer Assessment of TRACE
37th Annual CNS Conference , 1 (2017).
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Propagation of nuclear data uncertainties for fusion power measurements
EPJ Web of Conferences 146, 02034 (2017).DOI: 10.1051/epjconf/201714602034
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Radiative neutron capture: Hauser Feshbach vs. statistical resonances
PHYSICS LETTERS B 764, 109-113 (2017).DOI: 10.1016/j.physletb.2016.11.018
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SIMULATE-3K Analyses of Neutron Noise Response to Fuel Assembly Vibrations and Thermal-Hydraulics Parameters Fluctuations
M&C 2017: International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering P289, 1 (2017).
-
SiC CLADDING BEHAVIOR: EXPERIMENTS AND MODELLING AT PSI
2017 Water Reactor Fuel Performance Meeting, September 10-14, Jeju, Korea 2017, 1 (2017).
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TALYS/TENDL verification and validation processes: Outcomes and recommendations
EPJ Web of Conferences 146, 02033 (2017).DOI: 10.1051/epjconf/201714602033
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THERMAL HYDRAULIC ANALYSIS OF PWR ASSEMBLY BOWING USING SUBCHANNEL CODE COBRA-TF
NURETH 17: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 20409 (2017).
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THERMAL MIXING ASSESSMENT USING 3-D THERMAL-HYDRAULIC AND CFD CODES
NURETH 17: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics , 20714 (2017).
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Testing the NURESIM platform on a PWR main steam line break benchmark
NUCLEAR ENGINEERING AND DESIGN 321, 8-25 (2017).DOI: 10.1016/j.nucengdes.2017.05.028
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UO2 fuel pin bowing effects on isotopic concentrations
ANNALS OF NUCLEAR ENERGY 105, 361-368 (2017).DOI: 10.1016/j.anucene.2017.03.038
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Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly
PROGRESS IN NUCLEAR ENERGY 1, 1 (2017).DOI: 10.1016/j.pnucene.2017.05.033
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Worldwide activities
Molten Salt Reactors and Thorium Energy , 635 (2017).DOI: 10.1016/B978-0-08-101126-3.00026-9
2016
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A Bayesian Monte Carlo method for fission yield covariance information
ANNALS OF NUCLEAR ENERGY 95, 125-134 (2016).DOI: 10.1016/j.anucene.2016.05.005
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Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
NUCLEAR ENGINEERING AND DESIGN 305, 559-568 (2016).DOI: 10.1016/j.nucengdes.2016.06.021
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Analysis of selected Halden overpressure tests using the FALCON code
NUCLEAR ENGINEERING AND DESIGN 310, 395-409 (2016).DOI: 10.1016/j.nucengdes.2016.10.033
-
Bayesian Calibration of Thermal-Hydraulics Model with Time-Dependent Output
NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11P0491 (2016).
-
Bubble reconstruction method for wire-mesh sensors measurements
EXPERIMENTS IN FLUIDS 57, - (2016).DOI: 10.1007/s00348-016-2220-y
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Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data
NUCLEAR ENGINEERING AND DESIGN 300, 97-106 (2016).DOI: 10.1016/j.nucengdes.2015.11.023
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Comparison of Fission Yield Perturbation Methodologies on Nuclide Composition for a PWR UO2 Fuel Assembly
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
-
Developing an in situ EXAFS experiment of microwave-induced gelation
JOURNAL OF SOL-GEL SCIENCE AND TECHNOLOGY 78, 507 (2016).DOI: 10.1007/s10971-016-3992-5
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Evaluation of Deterministic Sampling for Uncertainty Quantification in a Probabilistic Accident Analysis Model
NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11P0291 (2016).
-
Experimental Validation of Control Rod Reactivity Worth and Fission Rate Distributions for the CROCUS Reactor
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
-
Fission yield covariances for JEFF: a Bayesian Monte Carlo method
International Conference on Nuclear Data for Science and Technology, Pts 1 and 2 2016, 1 (2016).
-
Full Core LOCA Analysis for BWR/6 - Methodology and First Results
TopFuel 2016: LWR Fuels with Enhanced Safety and Performance (Sep 11-16, 2016, Boise, Idaho, U.S.A.) 1, 1135 (2016).
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Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model Using the TRACE Code
NUCLEAR SCIENCE AND ENGINEERING 184, 400-429 (2016).DOI: 10.13182/NSE16-37
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Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
ND2013: International Conference on Nuclear Data for Science and Technology 2016, 1 (2016).
-
Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
International Conference on Nuclear Data for Science and Technology, Pts 1 and 2 2016, 1 (2016).
-
Influence of URANS Turbulence Models on In-Vessel Flow Mixing During Cold Leg Accumulator Injection
NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11P0292 (2016).
-
KMacs, AModular Adaptable Core Simulator
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
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Key Findings from the Artist Project on Aerosol Retention in a Dry Steam Generator
Nuclear Engineering and Technology 48, 870 (2016).DOI: 10.1016/j.net.2016.06.001
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Localized neutron flux assessment and verification studies using MCNPX PWR full core model
ANNALS OF NUCLEAR ENERGY 92, 317-332 (2016).DOI: 10.1016/j.anucene.2016.01.026
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Modeling and Analysis of selected OECD PKL3 Station-Blackout Experiments using TRACE
NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11A0310 (2016).
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Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation
ANNALS OF NUCLEAR ENERGY 92, 150-160 (2016).DOI: 10.1016/j.anucene.2016.01.042
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Nuclear data uncertainty propagation on spent fuel nuclide compositions
ANNALS OF NUCLEAR ENERGY 94, 603-611 (2016).DOI: 10.1016/j.anucene.2016.03.023
-
On Causality Analysis of Nuclear Reactor Noise using Partial Directed Coherence
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
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On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
PROGRESS IN NUCLEAR ENERGY 88, 43-52 (2016).DOI: 10.1016/j.pnucene.2015.11.015
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Po-210 poisoning as possible cause of death: forensic investigations and toxicological analysis of the remains of Yasser Arafat
FORENSIC SCIENCE INTERNATIONAL 259, 1-9 (2016).DOI: 10.1016/j.forsciint.2015.09.019
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Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
EPJ Nuclear Sci. Technol. 3, 3 (2016).DOI: 10.1051/epjn/2016040
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Re-evaluation of the thermal neutron capture cross section of Nd-147
ANNALS OF NUCLEAR ENERGY 94, 612-617 (2016).DOI: 10.1016/j.anucene.2016.03.024
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Recent research activities on high temperature pebble bed reactors at PSI
HTR 2016: Proceedings of the High Temperature Reactor Conference Las Vegas, United States, November 6-10, 2016 8, 135-140 (2016).
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Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
ANNALS OF NUCLEAR ENERGY 87, 48-57 (2016).DOI: 10.1016/j.anucene.2015.08.014
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Sampling of systematic errors to estimate likelihood weights in nuclear data uncertainty propagation
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 807, 137-149 (2016).DOI: 10.1016/j.nima.2015.10.024
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Selecting benchmarks for reactor simulations: An application to a lead fast reactor
ANNALS OF NUCLEAR ENERGY 96, 158-169 (2016).DOI: 10.1016/j.anucene.2016.05.033
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Simulation of Level-Swell Experiments with TRACE
NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11A0125 (2016).
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Solution of the Beavrs Benchmark using CASMO-5 / SIMULATE-5 Code Sequence
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
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Steady-state CFD simulations of an EPR (TM) reactor pressure vessel: A validation study based on the JULIETTE experiments
NUCLEAR ENGINEERING AND DESIGN 300, 41-56 (2016).DOI: 10.1016/j.nucengdes.2015.12.025
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System Code Validation Series based on a Consistent Plant Nodalisation of the ROSA/LSTF Integral Test Facility using TRACE v5.0 Patch 4
NUTHOS-11: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Oct 9-13, 2016, Gyeongju, Korea) 1, N11A0424 (2016).
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Testing the Sampling-Based NUSS-RF Tool for the Nuclear Data-Related Global Sensitivity Analysis with Monte Carlo Neutronics Calculations
NUCLEAR SCIENCE AND ENGINEERING 184, 69-83 (2016).DOI: 10.13182/NSE14-142
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The TENDL library: hope, reality and future
International Conference on Nuclear Data for Science and Technology, Pts 1 and 2 2016, 1 (2016).
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The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe e Part II: Thorium fuel cycle
PROGRESS IN NUCLEAR ENERGY 87, 144 (2016).DOI: 10.1016/j.pnucene.2014.11.016
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Towards a Consolidated Approach for the Assessment of Evaluation Models of Nuclear Power Reactors
NUCLEAR TECHNOLOGY 196, 223-237 (2016).DOI: 10.13182/NT16-47
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Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX
ANNALS OF NUCLEAR ENERGY 91, 48-58 (2016).DOI: 10.1016/j.anucene.2015.12.035
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Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
ANNALS OF NUCLEAR ENERGY 97, 153-164 (2016).DOI: 10.1016/j.anucene.2016.07.001
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Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions
ANNALS OF NUCLEAR ENERGY 97, 165 (2016).DOI: 10.1016/j.anucene.2016.07.015
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Validation of SIMULATE-3K against SPERT-III Ria Experiments with Quantification of Nuclear Data Uncertainties
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
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Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
ANNALS OF NUCLEAR ENERGY 96, 344-353 (2016).DOI: 10.1016/j.anucene.2016.06.016
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Verification of the New Implementations in SHARK-X for Reactivity Coefficients and Relative Reactivity Worth UQ
PHYSOR 2016: Unifying Theory and Experiments in the 21st Century 2016, 1 (2016).
2015
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A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics
PROGRESS IN NUCLEAR ENERGY 83, 82-98 (2015).DOI: 10.1016/j.pnucene.2015.02.014
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A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
ANNALS OF NUCLEAR ENERGY 85, 245 (2015).DOI: 10.1016/j.anucene.2015.05.008
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Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 52, 1084-1092 (2015).DOI: 10.1080/00223131.2015.1032382
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Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event
ANNALS OF NUCLEAR ENERGY 75, 645-657 (2015).DOI: 10.1016/j.anucene.2014.08.045
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Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR
ANNALS OF NUCLEAR ENERGY 85, 271-278 (2015).DOI: 10.1016/j.anucene.2015.05.023
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Assessment of OpenFOAM CFD Toolbox for Gravity Driven Mixing Flows in a Reactor Pressure Vessel
NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 952 (2015).
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Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions
ANNALS OF NUCLEAR ENERGY 87, 356 (2015).
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Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution
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).
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BWR Full Core Analysis with SERPENT/SIMULATE-3 Hybrid Stochastic/Determinstic Code Sequence
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).
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Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor
TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm , (2015).
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Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project
ANNALS OF NUCLEAR ENERGY 84, 86-97 (2015).DOI: 10.1016/j.anucene.2014.11.002
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COMPLINK: A Versatile Tool for Automatizing the Representation of Material Data in MCNP Models
ICNC 2015: International Cooperation in Nuclear Criticality Safety 1, 513 (2015).
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Computational Scheme for Burnup Credit applied to Long Term Waste Disposal
ICNC 2015: International Cooperation in Nuclear Criticality Safety 1, 1783 (2015).
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Criticality Safety Evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
ANNALS OF NUCLEAR ENERGY 83, 226-235 (2015).DOI: 10.1016/j.anucene.2015.03.052
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Delayed Neutron Fraction and Prompt Decay Constant Measurement in the MINERVE Reactor using the PSI Instrumentation
ANIMMA 2015: Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 20-24 April 2015, Lisbon 1, 1 (2015).
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Development, Verification and Test Application of a Hybrid CASMO-5/SERPENT Depletion Scheme
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 2015, 1 (2015).
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Fuel cycle analysis of a molten salt reactor for breed-and-burn mode
ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
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Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
ANNALS OF NUCLEAR ENERGY 85, 434-443 (2015).DOI: 10.1016/j.anucene.2015.05.004
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GeN-Foam: a novel OpenFOAM (R) based multi-physics solver for 2D/3D transient analysis of nuclear reactors
NUCLEAR ENGINEERING AND DESIGN 294, 24-37 (2015).DOI: 10.1016/j.nucengdes.2015.05.035
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Improving neutronics simulations and uncertainties via a selection of nuclear data
EUROPEAN PHYSICAL JOURNAL A 51, 182 (2015).DOI: 10.1140/epja/i2015-15182-0
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Methodology for Global Sensitivity Analysis of Transient Code Output applied to a Reflood Experiment Model using TRACE
NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 4862 (2015).
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Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL
Science and Technology of Nuclear Installations 2015, 237646 (2015).DOI: 10.1155/2015/237646
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Modeling of Axial Distribution of Released Fission Gas in KKL BWR Fuel Rods during Base Irradiation
TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm 1, 609 (2015).
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Modelling guidelines for core exit temperature simulations with system codes
NUCLEAR ENGINEERING AND DESIGN 286, 116-129 (2015).DOI: 10.1016/j.nucengdes.2015.02.003
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Multi-scale approach to advanced fuel modelling for enhanced safety
PROGRESS IN NUCLEAR ENERGY 84, 24-35 (2015).DOI: 10.1016/j.pnucene.2015.03.022
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NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 52, 1000-1007 (2015).DOI: 10.1080/00223131.2015.1040864
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NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method
ANNALS OF NUCLEAR ENERGY 75, 713-722 (2015).DOI: 10.1016/j.anucene.2014.09.013
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Neutron production and thermal moderation at the PSI UCN source
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
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Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
Journal of Nuclear Engineering and Radiation Science 1, 011009 (2015).DOI: 10.1115/1.4026401
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Particle deposition modeling in the secondary side of a steam generator bundle model
NUCLEAR ENGINEERING AND DESIGN , (2015).DOI: 10.1016/j.nucengdes.2015.09.001
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Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
TopFuel 2015: Reactor Fuel Performance (Sep 13-17, 2015, Zuerich, Switzerland) http://www.euronuclear.org/events/topfuel/topfuel2015/transactions.htm Paper A0109, (2015).
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Preparation of Pin-By-Pin Nuclear Libraries with Superhomogenization Method for Ntracer and Dort Core Calculations
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 2015, 1 (2015).
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Ranking of Uncertain Parameters for Dynamic Event Tree Analysis: A Case Study Based on a Station Blackout Scenario
NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 5734 (2015).
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Review of multi-physics temporal coupling methods for analysis of nuclear reactors
ANNALS OF NUCLEAR ENERGY 84, 225-233 (2015).DOI: 10.1016/j.anucene.2015.01.019
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Scalability Benchmarking Methodology for Hybrid Parallel Core Calculations with the Code nTRACER
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 2015, 1 (2015).
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Sodium Void Map Preparation for the Safety Analysis of Sodium-cooled Fast Reactors by Using the Monte Carlo Code Serpent
ICAPP 2015: Proceedings of the International Congress on Advances in Nuclear Power Plants 2015 , (2015).
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TOWARDS A CONSOLIDATED APPROACH FOR THE VALIDATION OF PLANT SYSTEM CODES AND MODELS: CASE STUDY FOR A BWR FAST DEPRESSURISATION EVENT
NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 1 (2015).
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TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark
NURETH 16: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics 1, 4757 (2015).
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Toward Reanalysis of the Tight-Pitch HCLWR-PROTEUS Phase II Experiments
Wonder 2015: Fourth International Workshop on Nuclear Data Evaluation for Reactor Applications 1, 1 (2015).
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Towards Application of Neutron Cross-Section Uncertainty Propagation Capability in the Criticality Safety Methodology
ICNC 2015: International Cooperation in Nuclear Criticality Safety 1, 606 (2015).
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Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
ANNALS OF NUCLEAR ENERGY 85, 820-829 (2015).DOI: 10.1016/j.anucene.2015.06.040
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Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis
ANNALS OF NUCLEAR ENERGY 77, 300-309 (2015).DOI: 10.1016/j.anucene.2014.11.019
2014
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AN INNOVATIVE APPROACH TO DYNAMICS MODELING AND SIMULATION OF THE MOLTEN SALT RECTOR EXPERIMENT
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104090 (2014).
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ANALYSIS OF THE OECD/NEA OSKARSHAMN-2 FEEDWATER TRANSIENT AND STABILITY BENCHMARK WITH SIMULATE-3K
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1101708 (2014).
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Analysis of Axial Fuel Relocation Based on Gamma Scan Data from OECD Halden Reactor Project LOCA Tests
WRFPM 2014 Proceedings, Sendai, Japan CD-ROM, 100041 (2014).
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Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related k(eff) Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark
NUCLEAR DATA SHEETS 118, 453-455 (2014).DOI: 10.1016/j.nds.2014.04.104
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Assessment of CFD URANS Models for Buoyancy Driven Mixing Flows Based on ROCOM Experiments
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1179 (2014).
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Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
NUCLEAR ENGINEERING AND DESIGN 278, 542-557 (2014).DOI: 10.1016/j.nucengdes.2014.08.007
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Assessment of TRACE against Single-Tube Post-Dryout Heat Transfer Experiments
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1192 (2014).
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CASMO-4E AND CASMO-5 ANALYSIS OF THE ISOTOPIC COMPOSITIONS OF THE LWR-PROTEUS PHASE II BURNT PWR UO2 FUEL SAMPLES
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104066 (2014).
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Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks
NUCLEAR DATA SHEETS 118, 388-391 (2014).DOI: 10.1016/j.nds.2014.04.088
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EFFECTS OF ADVANCED RADIAL SUBMESHING METHODS ON PIN POWER RECONSTRUCTION FOR AN EPR CORE DESIGN
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105669 (2014).
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Exploring Variability in Reflood Simulation Results: An Application of Functional Data Analysis
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1208 (2014).
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Hybrid spectrum molten salt reactor
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future , (2014).
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NEW PSI METHODOLOGY FOR MANUFACTURING AND TECHNOLOGICAL UNCERTAINTY QUANTIFICATION
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105694 (2014).
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Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
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Nuclear Data Library Effects on Fast to Thermal Flux Shapes Around PWR Control Rod Tips
NUCLEAR DATA SHEETS 118, 575-578 (2014).DOI: 10.1016/j.nds.2014.04.139
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On out-of-phase higher mode oscillations with rotation and oscillation of symmetry line using an advanced integral stability methodology
ANNALS OF NUCLEAR ENERGY 67, 21-30 (2014).DOI: 10.1016/j.anucene.2013.11.006
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PARAMETRIC LATTICE STUDY OF A GRAPHITE-MODERATED MOLTEN SALT REACTOR
ICONE 22: Proceedings of the 22nd International Conference on Nuclear Engineering 22, 31050 (2014).
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PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor
IGORR: International Group on Research Reactors, 17-21 November 2014, Bariloche, Argentina 1, 1 (2014).
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PINPOWER UNCERTAINTY QUANTIFICATION OF LWR-PROTEUS PHASE III EXPERIMENTS
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1099077 (2014).
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Post-test Analysis of OECD/NEA ROSA-2 Test 4 using TRACE
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1182 (2014).
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QUANTIFICATION OF CODE, LIBRARY AND CROSS-SECTION UNCERTAINTY EFFECTS ON THE VOID REACTIVITY COEFFICIENT OF A BWR UO2 ASSEMBLY
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1100815 (2014).
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Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
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Sensitivity Analysis of a Bottom Reflood Simulation using the Morris Screening Method
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1205 (2014).
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Simulation of flow in the secondary side of a steam generator bundle
CFD4NRS-5: Proceedings of the OECD/NEA & IAEA Workshop on Computational Fluid Dynamics for Nuclear Safety Research, ETH Zuerich, Switzerland, Sep. 9-11, 2014 1, 1 (2014).
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Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools
NUCLEAR DATA SHEETS 118, 498-501 (2014).DOI: 10.1016/j.nds.2014.04.117
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The Development and Implementation of a One-Dimensional S-n Method in the 2D-1D Integral Transport Solution
NUCLEAR SCIENCE AND ENGINEERING 176, 186-200 (2014).DOI: 10.13182/NSE12-4
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Treatment of Epistemic and Aleatory Uncertainties in DET Simulations: Computational Framework with ADS-TRACE
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1173 (2014).
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UNCERTAINTY AND SENSITIVITY ANALYSIS OF OECD/NEA UAM FUEL THERMAL BEHAVIOUR BENCHMARK USING A FALCON/URANIE METHODOLOGY
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105847 (2014).
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UNCERTAINTY QUANTIFICATION OF SPENT FUEL NUCLIDE COMPOSITIONS DUE TO CROSS SECTIONS, DECAY CONSTANTS AND FISSION YIELDS
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1104088 (2014).
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UPDATED VALIDATION OF THE PSI CRITICALITY SAFETY EVALUATION METHODOLOGY USING MCNPX2.7 AND ENDF/B-VII.1
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105709 (2014).
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Uncertainty- and Sensitivity Analysis of COBRA-TF for the Simulation of Selected OECD/NRC BFBT Void Experiments
NUTHOS-10: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Dec 14-18, 2014, Okinawa, Japan) 10, 1196 (2014).
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VALIDATION OF TWO MONTE CARLO CODES FOR LWR BURNUP CALCULATIONS
PHYSOR 2014: The Role of Reactor Physics Toward a Sustainable Future A, 1105825 (2014).
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VERIFICATION OF A REACTOR PHYSICS CALCULATION SCHEME FOR THE CROCUS REACTOR
ITMSR-3: 3rd International Technical Meeting on Small Reactors, 5-7 Nov 2015, Ottawa, Canada 1, 1 (2014).
-
Validation Enhancements of the PSI Fast Neutron Fluence Computational Scheme using Operational PWR Experimental Data
ANS Student Conference 2014, April 3-6, 2014, University Park, PA, USA , 1 (2014).
-
Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
Progress in Nuclear Science and Technology 4, 99 (2014).DOI: 10.15669/pnst.4.99
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X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization
PROGRESS IN NUCLEAR ENERGY 72, 91-95 (2014).DOI: 10.1016/j.pnucene.2013.09.009