Publications

Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM

A. Laureau; T. Le Meute; T. J-F. Ligonnet; E. Merle 

Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

F. B. Darby; O. V. Pakari; M. Y. Hua; V. Lamirand; S. D. Clarke et al. 

Enhancing higher education through hybrid and flipped learning: Experiences from the GRE@T-PIONEeR project

C. Demaziere; C. Stohr; Y. Zhang; O. Cabellos; S. Dulla et al. 

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

O. V. Pakari; A. Lucas; F. B. Darby; V. P. Lamirand; T. Maurer et al. 

Computation of sensitivity coefficients in fixed source simulations with SERPENT2

P. Griveaux; M. Hursin; I. Kodeli; D. Leichtle; A. Pautz 

High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS

T. Ligonnet; A. Laureau; A. Pautz; V. Lamirand 

Gamma noise to non-invasively monitor nuclear research reactors

O. Pakari; T. Mager; P. Frajtag; A. Pautz; V. Lamirand 

Intra-pin Reaction Rate Measurements in the CROCUS Experimental Reactor

T. Mager; O. Pakari; M. Hursin; T. Ligonnet; A. Pautz et al. 

Design of an Open-Loop Pile-Oscillation Program in the CROCUS Reactor

T. Ligonnet; A. Laureau; P. Simsbler; A. Pautz; V. Lamirand 

Atomic level insight into irradiation effects in nuclear fuel materials

Innovative thermophysical characterization of an ATF composite cladding: the case of silicon carbide

Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver

T. Guilbaud; C. Fiorina; A. Pautz; F. Carminati 

Monte Carlo analysis of BWR geometries using a cycle check-up methodology

M. Hursin; A. Vasiliev; D. Rochman; A. Dokhane; H. Ferroukhi 

Analysis of the preliminary campaign for the PETALE program

A. Laureau; A. Gruel; V. Lamirand; T. Ligonnet; A. Sardet et al. 

Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments

E. L. Brunetto; A. Scolaro; C. Fiorina; A. Pautz 

Design of an Instrumented Fuel Rod for Intra-pin Neutron Flux Measurements in the CROCUS Experimental Reactor

T. Mager; J-B. Valentin; V. Lamirand; T. Ligonnet; W. D. Shin et al. 

Development of a multi-channel gamma-blind fast neutron detector based on wavelength shifting fibers embedded in a ZnS:Ag epoxy mixture

A. Wolfertz; R. Adams; G. Perret; V. Lamirand 

Extension of GeN-Foam to departure from nucleate boiling prediction and validation against the OECD/NRC PSBT benchmark

Y. Niu; S. Alessandro; C. Fiorina; H. Qin; G. Lazare et al. 

Extension, validation, and optimization of Serpent/DYN3D/ATHLET code system for SFR applications

Microscopic Digital Image Correlation Analysis of Strain Distributions in Stainless Steel 316L Induced by Multiaxial Cyclic Loading

Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark

H. Qin; C. Fiorina; R. Zhang; S. Radman; D. Zhang et al. 

Gamma-Blind Fast Neutron Detection for Spent Nuclear Fuel Characterization

Unmoderated molten salt reactors design optimisation for power stability

A. Laureau; A. Belle; M. Allibert; D. Heuer; E. Merle et al. 

Towards coupling conventional with high-fidelity fuel behavior analysis tools

A. Scolaro; P. Van Uffelen; A. Schubert; C. Fiorina; E. Brunetto et al. 

High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties

O. V. Pakari; V. Lamirand; T. Mager; P. Frajtag; A. Pautz 

Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data

S. Radman; C. Fiorina; P. Song; A. Pautz 

Characterization of High Harmonic Frequencies in Reactor Noise Experiments Within the CORTEX Project

K. Ambrožič; V. P. Lamirand; A. Pautz 

Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors

T. Mager; C. Fiorina; M. Hursin; A. Pautz 

On the Capability of Wall-Modeled Large Eddy Simulations to Predict Particle Dispersion in Complex Turbulent Flows

Advanced methodologies for modeling and assessment of SFR safety functions

Towards implementing new isotopes for environmental research:Redetermination of the 32Si half-life

Miniature and Minimalistic Neutron Detectors for Online High-Resolution Experiments in the Zero-Power Reactor CROCUS

Delayed Hydride Cracking in Irradiated and Unirradiated Zircaloy-2 Cladding

GeN-ROM-An OpenFOAM(R)-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors

P. German; M. Tano; C. Fiorina; J. C. Ragusa 

Multi-physics modeling of VVERs with high fidelity high-resolution codes

On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM (R): state of the art, lessons learned and perspectives

C. Fiorina; I. Clifford; S. Kelm; S. Lorenzi 

Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5

A. Shama; D. Rochman; S. Caruso; A. Pautz 

Data-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear Fuel

Interface Tracking Investigation of the Sliding Bubbles Effects on Heat Transfer in the Laminar Regime

K. W. Wong; L. Bures; K. Mikityuk 

Development of a semi-implicit contact methodology for finite volume stress solvers

A. Scolaro; C. Fiorina; I. Clifford; A. Pautz 

Modeling the response of a diamond detector in the zero power reactor CROCUS

C. Kong; B. Ebiwonjumi; D. Lee; P. Kavrigin; C. Weiss et al. 

Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments

S. Radman; C. Fiorina; A. Pautz 

Delayed gamma fraction determination in the zero power reactor CROCUS

O. Pakari; T. Mager; V. Lamirand; P. Frajtag; A. Pautz 

Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

A. Shama; D. Rochman; S. Pudollek; S. Caruso; A. Pautz 

Hybrid halide perovskite neutron detectors

P. Andricevic; G. Nafradi; M. Kollar; B. Nafradi; S. Lilley et al. 

Study of a Current-Based Quench Detection Method for CCT Magnets via a Co-Wound Superconducting Sensing Wire

J. Gao; B. Auchmann; C. Hug; A. Pautz; S. Sanfilippo 

Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm

V. Solans; D. Rochman; C. Brazell; A. Vasiliev; H. Ferroukhi et al. 

Piecewise linear interface-capturing volume-of-fluid method in axisymmetric cylindrical coordinates

L. Bures; Y. Sato; A. Pautz 

Investigation on the effect of eccentricity for fuel disc irradiation tests

A. Scolaro; P. Van Uffelen; C. Fiorina; A. Schubert; I. Clifford et al. 

Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM

S. Radman; C. Fiorina; A. Pautz 

Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environments

W. Chen; P. Spatig; H. P. Seifert 

Characterization of Austenitic Stainless Steels with Regard to Environmentally Assisted Fatigue in Simulated Light Water Reactor Conditions

M. Bruchhausen; G. Dundulis; A. McLennan; S. Arrieta; T. Austin et al. 

Mean Stress Effect on the Fatigue Life of 304L Austenitic Steel in Air and PWR Environments Determined with Strain- and Load-Controlled Experiments

P. Spatig; J-C. Le Roux; M. Bruchhausen; K. Mottershead 

High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor

E. L. Brunetto; F. Vitullo; V. Lamirand; K. Ambrozic; D. Godat et al. 

Local and high distance neutron and gamma measurements of fuel rods oscillation experiments

V. Lamirand; O. Pakari; F. Vitullo; K. Ambrozic; D. Godat et al. 

First in-core gamma spectroscopy experiments in a zero power reactor

O. Pakari; V. Lamirand; T. Mager; A. Laureau; P. Frajtag et al. 

Design of a 150-miniature detectors 3D core-mapping system for the CROCUS reactor

F. Vitullo; V. Lamirand; K. Ambrozic; L. Braun; D. Godat et al. 

PISTIL, a reactivity modulation device to probe the transfer function of the nuclear reactor CROCUS

Y. Jiang; B. Geslot; V. Lamirand; P. Leconte; D. Godat et al. 

Fundamental study on microlayer dynamics in nucleate boiling

Improved methodology for analysis and design of Molten Salt Reactors

Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing-Part II: Methodology application

V. A. Di Nora; E. Fridman; E. Nikitin; Y. Bilodid; K. Mikityuk 

Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media

P. German; M. E. Tano; C. Fiorina; J. C. Ragusa 

Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise

I. Pazsit; L. A. Torres; M. Hursin; H. Nylen; V. Dykin et al. 

Development of a Novel Finite Volume Methodology for Multi-Dimensional Fuel Performance Applications

A Coarse-mesh Methodology for the Analysis of One and Two-phase Nuclear Reactor Thermal-hydraulics in a Multi-physics Context

Structural performance and mechanical properties investigation of spent nuclear fuel rods under static and dynamic bending loads

Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: Methodology demonstration

V. A. Di Nora; E. Fridman; E. Nikitin; Y. Bilodid; K. Mikityuk 

Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor

A. S. Vanyi; B. Babcsany; Z. Boroczki; A. Horvath; M. Hursin et al. 

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters (vol 370, 110897, 2020)

V. Solans; D. Rochman; H. Ferroukhi; A. Vasiliev; A. Pautz 

Validation of axial void profile measured by neutron noise techniques in CROCUS

M. Hursin; O. Pakari; G. Perret; P. Frajtag; V. Lamirand et al. 

CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements

A. G. Mylonakis; C. Demazière; P. Vinai; V. Lamirand; A. Rais et al. 

Towards the Validation of Noise Experiments in the CROCUS Reactor Using the TRIPOLI-4 Monte Carlo Code in Analog Mode

O. Pakari; D. Mancusi; O. Petit; A. Zoia; V. Lamirand et al. 

Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX

V. Lamirand; A. Rais; O. Pakari; M. Hursin; A. Laureau et al. 

Dosimetry modeling and experimental validation for the PETALE program in the CROCUS reactor

A. Laureau; V. Lamirand; A. Gruel; P. Frajtag; A. Pautz 

Highly localized azimuthal measurements in the CROCUS reactor towards the validaiton of high-fidelity neutronics codes

F. Vitullo; V. Lamirand; P. Frajtag; G. Perret; A. Pautz 

A Hybrid Approach to Neutron Transport with Thermal-hydraulic Feedback for Reactor Transient Analysis

APT/TEM characterization of the element segregation in ferritic/martensitic steels after irradiation in SINQ

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

V. Solans; D. Rochman; H. Ferroukhi; A. Vasiliev; A. Pautz 

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

C. Fiorina; A. Scolaro; D. J. Siefman; M. Hursin; A. Pautz 

Development and verification of a methodology for neutron noise response to fuel assembly vibrations

D. Chionis; A. Dokhane; L. Belblidia; H. Ferroukhi; G. Girardin et al. 

First observation of spalling in tantalum at high temperatures induced by high energy proton beam impacts

C. Torregrosa Martin; N. Solieri; E. Fornasiere; J. Busom Descarrega; M. Calviani et al. 

Circularly Polarized Transmitarray Antenna for CubeSat Intersatellite Links in K-Band

M. J. Veljovic; A. K. Skrivervik 

Dynamic study of contact damping in martensitic stainless steels using nano-indentation

R. Mouginot; P. Spatig; H-P. Seifert 

Data assimilation of post-irradiation examination data for fission yields from GEF

D. Siefman; M. Hursin; H. Sjostrand; G. Schnabel; D. Rochman et al. 

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

F. Bostelmann; B. T. Rearden; W. Zwermann; A. Pautz 

Modeling of Quench Protection Concepts for Canted-Cosine-Theta Type High-Field Magnets

J. Gao; B. Auchmann; L. Brouwer; A. Pautz; S. Sanfilippo 

Uncertainty propagation based on correlated sampling technique for nuclear data applications

A. Laureau; V. Lamirand; D. Rochman; A. Pautz 

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

A. Laureau; V. Lamirand; D. Rochman; A. Pautz 

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

F. Vitullo; V. Lamirand; J-B. Mosset; P. Frajtag; O. Pakari et al. 

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

F. Vitullo; J. Krepel; J. Kalilainen; H-M. Prasser; A. Pautz 

Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments

D. Siefman; M. Hursin; G. Perret; A. Pautz 

The OFFBEAT multi-dimensional fuel behavior solver

A. Scolaro; I. Clifford; C. Fiorina; A. Pautz 

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

A. Aures; N. Berner; A. Pautz; W. Zwermann 

Measurement of the Gas Velocity in a Water-Air Mixture in CROCUS Using Neutron Noise Techniques

M. Hursin; O. Pakari; G. Perret; P. Frajtag; V. Lamirand et al. 

Noise analysis techniques of in-core modulation experiments of the European CORTEX project

K. Ambrožič; V. P. Lamirand; S. Hübner; M. Hursin; A. Rais et al. 

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

V. Lamirand; A. Rais; S. Huebner; C. Lange; J. Pohlus et al. 

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

Y. Jiang; A. Laureau; V. Lamirand; P. Frajtag; A. Pautz 

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

O. Pakari; V. Lamirand; B. Vandereydt; F. Vitullo; M. Hursin et al. 

Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS

F. Vitullo; V. Lamirand; J-B. Mosset; P. Frajtag; O. Pakari et al. 

Power calibration methodology at the CROCUS reactor

V. Lamirand; A. Laureau; O. Pakari; P. Frajtag; A. Pautz 

Data assimilation of post irradiation examination experiments to adjust fission yields

D. Siefman; M. Hursin; A. Pautz 

Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations

A. Vasiliev; M. Pecchia; D. Rochman; G. Perret; H. Ferroukhi et al. 

Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation

A. Laureau; V. Lamirand; D. Rochman; A. Pautz 

The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator

V. Lamirand; P. Frajtag; D. Godat; O. Pakari; A. Laureau et al. 

Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows

P. German; M. Tano; J. C. Ragusa; C. Fiorina 

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

F. Grimberg 

Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

M. R. Altahhan; S. Bhaskar; D. Ziyad; P. Balestra; C. Fiorina et al. 

Adaptive Regularization For Three-Dimensional Optical Diffraction Tomography

T-a. Pham; E. Soubies; A. Ayoub; D. Psaltis; M. Unser 

Post-irradiation examination of refractory metal candidates for antiproton targets at the European Laboratory for Particle Physics (CERN)

Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments

Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores

Analysis of Quench Detection and Protection of a Nb3Sn CCT Technology Demonstrator Dipole for FCC

The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs

B. Hombourger; J. Krepel; A. Pautz 

Experimental and numerical study of stochastic branching noise in nuclear reactors

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients

D. Siefman; M. Hursin; M. Aufiero; A. Bidaud; A. Pautz 

Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

D. Rochman; A. Dokhane; A. Vasiliev; H. Ferroukhi; M. Hursin 

Treatment of the implicit effect in Shark-X

M. Hursin; S. Pelloni; A. Vasiliev; H. Ferroukhi 

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

Reactor simulations with nuclear data uncertainties

A. Aures; W. Bernnat; F. Bostelmann; J. Bousquet; B. Krzykacz-Hausmann et al. 

A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design

S. Radman; C. Fiorina; K. Mikityuk; A. Pautz 

Breed-and-burn fuel cycle in molten salt reactors

B. Hombourger; J. Krepel; A. Pautz 

Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments

Z. Que; H. Seifert; P. Spätig; A. Zhang; J. Holzer et al. 

Application of causality analysis on nuclear reactor systems

D. Chionis; A. Dokhane; H. Ferroukhi; A. Pautz 

GEN-FOAM: An OpenFOAM (R)-Based Multi-physics Solver for Nuclear Reactor Analysis

C. Fiorina 

Viability limits of the renewable source in an electricity mix: The MIXOPTIM analysis methodology

B. Bonin; A. Laureau; G. Krivtchik; G. Bordier; H. Safa et al. 

Application of multiphysics model order reduction to doppler/neutronic feedback

P. German; J. C. Ragusa; C. Fiorina 

Towards the validation of neutron noise simulators: qualification of data acquisition systems

A. Rais; V. P. Lamirand; O. V. Pakari; A. Laureau; J. Pohlus et al. 

Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique

M. Hursin; O. V. Pakari; G. Perret; P. Frajtag; V. P. Lamirand et al. 

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor

W. Kim; M. Hursin; A. Pautz; L. Vincent; F. Pavel et al. 

Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors

C. Fiorina 

An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor

V. P. Lamirand; A. Laureau; D. Rochman; G. Perret; A. Gruel et al. 

Development and Application of Data Assimilation Methods in Reactor Physics

Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels

A. Shama; M. A. Pouchon; I. Clifford 

Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations

P. Blaise; A. Laureau; P. Ros; P. Leconte; K. Routsonis 

High-Temperature Water Effects on the Fracture Behaviour of Low-Alloy Reactor Pressure Vessel Steels

High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

Extension of the nodal code DYN3D to SFR applications

Response of irradiated nuclear fuel rods to quasi-static and dynamic loads

E. Vlassopoulos; R. Nasyrow; D. Papaioannou; R. Gretter; L. Fongaro et al. 

A reduced order accelerator for time-dependent segregated neutronic solvers

C. Fiorina; S. Radman; A. Scolaro; A. Pautz 

Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments

D. Siefman; M. Hursin; D. Rochman; S. Pelloni; A. Pautz 

Kinetic Parameter Measurements in the CROCUS Reactor Using Current Mode Instrumentation

O. Pakari; V. Lamirand; G. Perret; P. Frajtag; A. Pautz 

Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS

O. V. Pakari; V. P. Lamirand; G. Perret; D. Godat; M. Hursin et al. 

Intercomparison of neutron noise measurement systems in the CROCUS reactor

V. P. Lamirand; G. de Izarra; A. Krása; G. Perret; O. V. Pakari et al. 

Testing of a sCVD diamond detection system in the CROCUS reactor

M. Hursin; C. Weiss; P. Frajtag; V. Lamirand; G. Perret et al. 

Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor

A. Laureau; V. P. Lamirand; D. Rochman; A. Pautz 

Design of Separated Element Reflector Experiments in CROCUS: PETALE

V. Lamirand; G. Perret; S. Ragman; D. Siefman; P. Frajtag et al. 

Statistical Burnup Distribution Of Moving Pebbles In Htr-Pm Reactor

F. Vitullo; J. Krepel; J. Kalilainen; H-M. Prasser; A. Pautz 

First Steps Towards The Development Of A 3D Nuclear Fuel Behavior Solver With Openfoam

A. Scolaro; I. Clifford; C. Fiorina; A. Pautz 

Cfd-Based Correlation For Forced Convection Heat Transfer In Circular Ducts Of Internally Heated Molten Salts

F. Di Lecce; S. Dulla; P. Ravetto; A. Cammi; S. Lorenzi et al. 

Creation Of An Openfoam Fuel Performance Class Based On Fred And Integration Into The Gen-Foam Multi-Physics Code

C. Fiorina; A. Pautz; K. Mikityuk 

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

S. Radman; C. Fiorina; K. Mikityuk; A. Pautz 

Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interface

A. W. Colldeweih; A. Baris; P. Spätig; S. Abolhassani 

Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification

R. G. G. de Oliveira; K. Mikityuk 

Pin-by-Pin Treatment of LWR Cores with Cross Section Equivalence Procedures and Higher-Order Transport Methods

Conceptual Design of a Sustainable Waste Burning Molten Salt Reactor

Investigations and numerical modeling of mechanical properties of tempered martensitic steel Eurofer97 at various loading rates, temperatures and after spallation irradiation

Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor

Characterisation of the activation in Crocus

V. Chaussonnet 

Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes

D. J. Siefman; M. Hursin; M. Aufiero; A. Bidaud; A. Pautz 

Bayesian Uncertainty Quantification of Physical Models in Thermal-Hydraulics System Codes

Helium effects on irradiation assisted stress corrosion cracking susceptibility of 316L austenitic stainless steel

Method development for discrimination of anodic and cathodic signals in miniature fission chambers for reactor physics applications

A. Theler 

Design of Separated Element Reflector Experiments in CROCUS: PETALE

V. P. Lamirand; G. Perret; S. Radman; D. J. Siefman; M. Hursin et al. 

Effect of residual stresses on notch toughness of the tempered martensitic steel F82H-MOD

N. Ilchuk; V. Davydov; P. Spätig; H-P. Seifert 

CROCUS Concrete Activation Study by γ-ray Spectrometry and TLD Neutron Flux Measurements

I. Tanseri 

Concrete and Metallic Structures Activation Calculations

H. Gavotto 

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

A. Rais; D. J. Siefman; M. Hursin; A. Ward; A. Pautz 

Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor

Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model

P. Grimm; M. Hursin; G. Perret; D. Siefman; H. Ferroukhi 

Case Study of Data Assimilation Methods with the LWR-Proteus Phase II Experimental Campaign

D. J. Siefman; M. Hursin; P. Grimm; A. Pautz 

Development of Current and Fast Neutron Noise Measurements in CROCUS

O. V. Pakari 

Development of an experimental channel in CROCUS

A. Theler 

An inverse method based on finite element model to derive the plastic flow properties from non-standard tensile specimens of Eurofer97 steel

S. Knitel; P. Spätig; H. P. Seifert 

Future experimental programmes in the CROCUS reactor

V. P. Lamirand; M. Hursin; G. Perret; P. Frajtag; O. Pakari et al. 

Neutron noise measurement in current mode

O. V. Pakari 

Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor

D. J. Siefman; G. Girardin; A. Rais; M. Hursin; A. Pautz 

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

A. Rais; D. J. Siefman; G. Girardin; M. Hursin; A. Pautz 

Uncertainty Quantification and Representativity Analysis of the LWR-PROTEUS Phase II Experimental Campaign

D. J. Siefman 

Embrittlement induced by the synergistic effects of radiation damage and helium in structural steels

A Methodology for Global Sensitivity Analysis for Time-Dependent Code Output Applied to Reflood Simulation in TRACE

D. C. Wicaksono; O. Zerkak; A. Pautz 

Sampling-Based Nuclear Data Uncertainty Quantification for Continuous Energy Monte Carlo Codes

Verification of a reactor physics calculation scheme for the CROCUS reactor

M. Hursin; D. J. Siefman; A. Rais; G. Girardin; A. Pautz 

Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools

H. Ferroukhi; O. Leray; M. Hursin; A. Vasiliev; G. Perret et al. 

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

T. Zhu; A. Vasiliev; H. Ferroukhi; A. Pautz 

Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks

T. Zhu; D. Rochman; A. Vasiliev; H. Ferroukhi; W. Wieselquist et al. 

Exploring Variability in Reflood Simulation Results: an Application of Functional Data Analysis

D. C. Wicaksono; O. Zerkak; A. Pautz 

Sensitivity Analysis of a Bottom Reflood Simulation using Morris Screening Method

D. C. Wicaksono; O. Zerkak; A. Pautz 

Experimental tests of an advanced proton-to-neutron converter at ISOLDE-CERN

A. Gottberg; T. M. Mendonca; R. Luis; J. P. Ramos; C. Seiffert et al. 

Validation of Two Monte Carlo Codes for LWR Burnup Calculations

D. C. Wicaksono; P. Grimm; A. Vasiliev; M. Hursin; G. Perret et al. 

Experimental Validation of 3-D Reconstructed Pin Power Distributions in Full-Scale BWR Fuel Assemblies with Partial-Length Rods

F. D. Giust; P. Grimm; R. Chawla 

Application of Power Time-Projection on the Operator Splitting Coupling Scheme of the TRACE/S3K Coupled Code

D. C. Wicaksono; O. Zerkak; K. Nikitin; H. Ferroukhi; R. Chawla 

Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study For Improving The Response Of A 3600 Mw(Thermal) Sfr Core To An Unprotected Loss-Of-Flow Accident

K. Sun; A. Chenu; J. Krepel; K. Mikityuk; R. Chawla 

Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor

H. Kroehnert; G. Perret; M. F. Murphy; R. Chawla 

Analysis of selected Phenix EOL tests with the FAST code system – Part II: Unprotected phase of the Natural Convection Test

A. Chenu; K. Mikityuk; R. Chawla 

Analysis of selected Phenix EOL tests with the FAST code system – Part I: Control-rod-shift experiments

A. Chenu; R. Adams; K. Mikityuk; R. Chawla 

A novel design approach for a neutron measurement station for burnt fuel

R. Dietler; M. Hursin; G. Perret; K. Jordan; R. Chawla 

Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics

Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice

D. Raetz; K. A. Jordan; A-S. P. Bayard; G. Perret; R. Chawla 

Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX

A. Marinoni; G. Girardin; K. Mikityuk 

A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions

A. Epiney; N. Alpy; K. Mikityuk; R. Chawla 

Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs

Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies

Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies

F. D. Giust; P. Grimm; R. Chawla 

Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip

P. Vinai; R. Macian-Juan; R. Chawla 

Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE algorithm

D. Bertolotto; A. Manera; R. Macian-Juan; R. Chawla 

Comparison of measured and calculated reaction rate distributions in an scwr-like test lattice

D. Raetz; K. A. Jordan; M. F. Murphy; G. Perret; R. Chawla 

Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle

K. Sun; J. Krepel; K. Mikityuk; S. Pelloni; R. Chawla 

Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark

R. Pittarello; A. Vasiliev; H. Ferroukhi; R. Chawla 

Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice

D. Raetz; K. A. Jordan; G. Perret; R. Chawla 

Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow

A. Chenu; K. Mikityuk; R. Chawla 

Coupling a System Code with Computational Fluid Dynamics for the Simulation of Complex Coolant Reactivity Effects

Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors

Fission Rates Measured Using High-Energy Gamma-Rays from Short Half-Life Fission Products in Fresh and Spent Nuclear Fuel

Experimental validation of radial reconstructed pin-power distributions in full-scale BWR fuel assemblies with and without control blade

F. Giust; P. Grimm; R. Chawla 

Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions

A. Epiney; K. Mikityuk; R. Chawla 

Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel

H. Krohnert; G. Perret; M. F. Murphy; R. Chawla 

TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods

A. Epiney; K. Mikityuk; R. Chawla 

FAST code system: Review of recent developments and near-future plans

K. Mikityuk; J. Krepel; S. Pelloni; A. Chenu; P. Petkevich et al. 

Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor

Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

M. Plaschy; M. Murphy; F. Jatuff; G. Perret; R. Seiler et al. 

Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades

M. Plaschy; M. Murphy; F. Jatuff; A. Luthi; P. Grimm et al. 

Development and benchmarking of a mechanical model for GFR plate-type fuel

P. Petkevich; K. Mikityuk; P. Coddington; R. Chawla 

Impact of new gadolinium cross sections on reaction rate distributions in 10×10 BWR assemblies

G. Perret; M. F. Murphy; F. Jatuff; J. C. Sublet; O. Bouland et al. 

Void reactivity coefficient benchmark results for a 10×10 BWR assembly in the full 0-100% void fraction range

F. Jatuff; G. Perret; M. F. Murphy; F. Giust; R. Chawla 

Cross-section modelling effects on pressurised water reactor main steam line break analyses

H. Ferroukhi; O. Zerkak; R. Chawla 

Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme

H. Ferroukhi; J. M. Hollard; M. A. Zimmermann; R. Chawla 

TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions

A. Chenu; K. Mikityuk; R. Chawla 

Editorial

R. Chawla 

Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography

S. Caruso; M. F. Murphy; F. Jatuff; R. Chawla 

Single-phase mixing studies by means of a directly coupled CFD/system-code tool

D. Bertolotto; A. Manera; S. Frey; H. M. Prasser; R. Chawla 

Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR)

Validation of Monte-Carlo simulations with measurements at the ICON beam-line at SINQ

L. Giller; U. Filges; G. Kuehne; M. Wohlmuther; L. Zanini 

On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations

A. Vasiliev; E. Kolbe; H. Ferroukhi; M. A. Zimmermann; R. Chawla 

On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test

A. Vasiliev; H. Ferroukhi; M. A. Zimmermann; R. Chawla 

Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly

G. Perret; M. Plaschy; M. F. Murphy; F. Jatuff; R. Chawla 

Comparison of 3D reaction rate distributions measured in an optima2 BWR assembly with MCNPX predictions

M. F. Murphy; F. Jatuff; G. Perret; M. Plaschy; U. Bergmann et al. 

Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor

G. Girardin; G. Rimpault; F. Morin; J. C. Bosq; P. Coddington et al. 

Management of actinide waste inventories in nuclear phase-out scenarios

M. Cometto; P. Wydler; R. Chawla 

Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+ test lattice

R. Chawla; F. Jatuff; F. Tani 

Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography

S. Caruso; M. F. Murphy; F. Jatuff; R. Chawla 

Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2

S. Caruso; I. Gunther-Leopold; M. F. Murphy; F. Jatuff; R. Chawla 

Interpretation of high-burnup fuel annealing tests

P. Blair; G. Khvostov; A. Romano; C. Hellwig; R. Chawla 

Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor

Modelling of fission gas behaviour in high burnup nuclear fuel

A statistical methodology for quantification of uncertainty in best estimate code physical models

P. Vinai; R. Macian-Juan; R. Chawla 

Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data

A. Vasiliev; H. Ferroukhi; M. A. Zimmermann; R. Chawla 

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel

P. Petkevich; K. Mikityuk; P. Coddington; R. Chawla 

Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic-cooled reactor systems

K. Mikityuk; P. Coddington; S. Pelloni; E. Bubelis; R. Chawla 

Radial and azimuthal 235U fission and 238U capture distributions in BWR UO2 pins: CASMO-4 and MCNP4C versus activation foil measurements

K. Macku; F. Jatuff; M. Murphy; M. Plaschy; P. Grimm et al. 

Statistical uncertainty analysis applied to fuel depletion calculations

R. Macian; M. A. Zimmermann; R. Chawla 

Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel

S. Caruso; M. Murphy; F. Jatuff; R. Chawla 

Investigations of238U captures to total fissions in a Westinghouse SVEA-96+ assembly

U. C. Bergmann; P. Grimm; F. Jatuff; M. F. Murphy; R. Chawla 

BWR stability and bifurcation analysis using reduced order models and system codes: Identification of a subcritical Hopf bifurcation using RAMONA

A. Dokhane; D. Hennig; u. Rizwan; R. Chawla 

Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis

A. Dokhane; D. Hennig; u. Rizwan; R. Chawla 

Development and application of objective uncertainty measures for nuclear power plant transient analysis

Characterisation of high-burnup LWR fuel rods through gamma tomography

Absolute depth-dose-rate measurements for an 192Ir HDR brachytherapy source in water using MOSFET detectors

V. O. Zilio; O. P. Joneja; Y. Popowski; A. Rosenfeld; R. Chawla 

Isobaric production cross sections from 0.6 GeV proton irradiation of neptunium and thorium using mass spectrometry

H. U. Wenger; A. A. Mazouzi; F. Atchison; M. Burghartz; R. Chawla et al. 

Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code

A. Romano; H. Wallin; M. A. Zimmermann; R. Chawla 

Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades

M. Plaschy; F. Jatuff; P. Grimm; F. Tani; R. Jacot-Guillarmod et al. 

Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques

M. Plaschy; C. Destouches; R. Chawla; D. Beretz; F. Mellier et al. 

Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples

M. F. Murphy; F. Jatuff; P. Grimm; R. Seiler; R. Brogli et al. 

Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems

K. Mikityuk; P. Coddington; E. Bubelis; R. Chawla 

Advanced foil activation techniques for the measurement of within-pin distributions of the 63Cu(n,)64Cu reaction rate in nuclear fuel

K. Macku; F. Jatuff; M. F. Murphy; O. P. Joneja; R. Bischofberger et al. 

Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+ BWR assembly

F. Jatuff; F. Tani; R. Chawla 

On the accuracy of reactor physics calculations for square HPLWR fuel assemblies

F. Jatuff; K. Macku; R. Chawla 

Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 1010 BWR assembly

F. Jatuff; F. Giust; J. Krouthen; S. Helmersson; R. Chawla 

Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly

P. Grimm; F. Jatuff; M. Murphy; R. Seiler; T. Williams et al. 

A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor

R. Chawla; J. M. Paratte; R. Fruh; U. Kasemeyer; M. A. Kalugin et al. 

Calculations on fission gas behaviour in the high burnup structure

P. Blair; A. Romano; C. Hellwig; R. Chawla 

Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel

U. C. Bergmann; R. Chawla; F. Jatuff; M. F. Murphy 

Decomposition analysis of reactivity effect predictions for modern LWR fuel

144Ce as a potential candidate for interstitial and intravascular brachytherapy

V. O. Zilio; O. P. Joneja; Y. Popowski; F. O. Bochud; R. Chawla 

Importance of the MUSE experiments for emerging ADS concepts from the nuclear data viewpoint

M. Plaschy; S. Pelloni; P. Coddington; G. Rimpault; R. Chawla 

Investigation of ADS-Type heterogeneities in the MUSE4 critical configuration

M. Plaschy; C. Destouches; G. Rimpault; R. Chawla 

Calculation of multiple-scattering angular distributions of electrons and positrons

C. Negreanu; X. Llovet; R. Chawla; F. Salvat 

FAST: An advanced code system for fast reactor transient analysis

K. Mikityuk; S. Pelloni; P. Coddington; E. Bubelis; R. Chawla 

Development of a drift-flux model for heavy liquid metal/gas flow

K. Mikityuk; P. Coddington; R. Chawla 

Within-pin 238U-capture distributions: CASMO-4 and MCNP vs. activation foil measurements

K. Macku; F. Jatuff; M. Murphy; P. Grimm; O. P. Joneja et al. 

Within-pin reaction rate distributions: CASMO-4 and HELIOS compared against tomographic measurements at the PROTEUS reactor

C. P. Fauchere; M. Murphy; F. Jatuff; R. Chawla 

Development and validation of data sets and Monte Carlo methods for electron/positron transport at low and medium energies

Développement et validation de méthodes dosimétriques en ligne pour le traitement du cancer de la prostate

Quantification of the transferability of reactivity effect investigations in large multiregion systems

R. van Geemert; F. Jatuff; F. Tani; R. Chawla 

Development and application of a decomposition methodology for interpretation of reactivity effect discrepancies

R. van Geemert; F. Jatuff; F. Tani; R. Chawla 

Adapting and applying SPECT to the investigation of reaction rate distributions within lightly activated nuclear fuel pins

C. Pralong Fauchere; F. Jatuff; M. Murphy; R. Chawla 

Experimental Determination of the Ratio of 238U Capture to 235U Fission in LEU-HTR Pebble-Bed Configurations

O. Koberl; R. Seiler; R. Chawla 

Plutonium management in the medium term

K. Hesketh; G. Schlosser; D. F. Porsch; T. Wolf; O. Koberl et al. 

A comparative physics study of alternative long-term strategies for closure of the nuclear fuel cycle

M. Cometto; P. Wydler; R. Chawla 

Etudes numériques et expérimentales de caractéristiques d’un système rapide sous-critique alimenté par une source externe

BWR stability and bifurcation analysis using a novel reduced order model and the system code RAMONA

The effect of nuclear data on the MCNPX modeling of moderator level variations in the CROCUS critical facility

J. R. Lebenhaft; R. Fruh; R. Chawla 

Comparison of Monte Carlo simulations of photon/electron dosimetry in microscale applications

O. P. Joneja; C. Negreanu; J. Stepanek; R. Chawla 

Measurement and interpretation of delayed photoneutron effects in multizone criticals with partial D2O moderation

F. Jatuff; A. Luthi; M. Murphy; T. Williams; R. Chawla 

Validation of axial pin power distributions in a 1010 BWR assembly across an enrichment boundary under full-density water moderation conditions

F. Jatuff; P. Grimm; R. van Geemert; M. Murphy; R. Seiler et al. 

Interpretation of experimental results from moderate-power in-pile testing of a Pu-Er-Zr-oxide inert matrix fuel

C. Hellwig; U. Kasemeyer; G. Ledergerber; L. Byung-Ho; L. Young-Woo et al. 

Standardisation des outils de calcul pour les ADS et leur application à différents scénarios de transmutation des déchets

Investigation of within-pin reaction rate distributions in a highly heterogeneous BWR fuel assembly

Assessment of reactivity effects due to localized perturbations in BWR lattices

R. Van Geemert; F. Jatuff; P. Grimm; R. Chawla 

Neutronics investigations for the lower part of a Westinghouse SVEA-96+ assembly

M. F. Murphy; A. Luthi; R. Seiler; P. Grimm; O. Joneja et al. 

Application and in-depth assessment of RETRAN-3D for best estimate analysis of nuclear power plant transients

P. Coddington; R. Macian; M. A. Zimmermann; R. Chawla 

Numerical neutronics benchmark study for inert matrix plutonium fuels in uranium dioxide and mixed plutonium-uranium dioxide environments

J. M. Paratte; R. Chawla; H. Akie; P. M. G. Damen; H. K. Joo et al. 

Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations

A. Luthi; R. Chawla; G. Rimpault 

Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI, and JEF-2.2 cross-section libraries

O. P. Joneja; M. Plaschy; F. Jatuff; A. Luthi; M. Murphy et al. 

LWR-PROTEUS verification of reaction rate distributions in modern 10×10 boiling water reactor fuel

F. Jatuff; P. Grimm; O. Joneja; M. Murphy; A. Luthi et al. 

Categorisation and priorities for future research on inert matrix fuels: an extended synthesis of the panel discussions

R. Chawla; R. J. M. Konings 

Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice

R. Chawla; P. Grimm; P. Heimgartner; F. Jatuff; G. Ledergerber et al. 

Importance of zirconium cross sections in calculating reactivity effects for inert matrix fuels

S. Baldi; J. Porta; Y. Peneleau; S. Pelloni; J. M. Paratte et al. 

On the modeling of reactivity initiated accidents in light water reactor cores containing high-burnup fuel

Epithermal inverse kinetic measurements and their interpretation using a two-group point-kinetic model

M. Rosselet; R. Chawla; T. Williams 

Comparisons of cell calculations for uranium-free light water reactor fuels

J-M. Paratte; H. Akie; R. Chawla; M. Delpech; J. L. Kloosterman et al. 

Characterisation of MCP-7s- material for use as a beta extremity dosemeter

M. Boschung; A. Hornsy; O. P. Joneja; R. Chawla 

A high-fluence 0.6 GeV proton irradiation experiment with thin uranium and thorium targets

H. U. Wenger; F. Botta; R. Chawla; M. Daum; D. Gavillet et al. 

Conceptual studies for pressurized water reactor cores employing plutonium-erbium-zirconium oxide inert matrix fuel assemblies

A. Stanculescu; U. Kasemeyer; J. M. Paratte; R. Chawla 

Investigation of the keff-variation upon water ingress in a pebble-bed LEU-HTR

M. Rosselet; R. Chawla; T. Williams 

Validation efforts for the neutronics of a plutonium-erbium-zirconium oxide inert matrix light water reactor fuel

J. M. Paratte; R. Chawla; R. Fruh; O. P. Joneja; S. Pelloni et al. 

Reactivity measurements and their interpretation in systems with large spatial effects

Development and validation of gamma-heating calculational methods for plutonium-burning fast reactors

Subcriticality measurements using an epithermal pulsed-neutron-source technique in pebble-bed HTR configurations

M. Rosselet; T. Williams; R. Chawla 

Impact of methods and data on calculational results for LWR lattices employing uranium free plutonium fuels

S. Pelloni; U. Kasemeyer; J. M. Paratte; R. Chawla 

Comparison of pressurized water reactor core characteristics for 100% plutonium-containing loadings

U. Kasemeyer; J. M. Paratte; P. Grimm; R. Chawla 

Experimentelle Neutronenbilanzuntersuchungen zum Wassereinbruch in einen [i.e. “einem”] Hochtemperaturreaktor mit niedrig angereichertem Uranbrennstoff

Konzeption eines uranfreien LWR-Kerns zur Plutoniumverbrennung

On the physics feasibility of LWR plutonium fuels without uranium

J. M. Paratte; R. Chawla 

Determination of absolute tool wear by γ-γ coincidence counting of radiotracers

R. Chawla; S. L. Bhattacharya