Publications

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

A. Cavaliere / M. A. Pouchon; C. Cozzo (Dir.)  

Lausanne, EPFL, 2024. 

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

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

Progress In Nuclear Energy. 2023-12-07. Vol. 168, p. 104980. DOI : 10.1016/j.pnucene.2023.104980.

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. 

Nuclear Engineering And Design. 2023-11-14. Vol. 416, p. 112748. DOI : 10.1016/j.nucengdes.2023.112748.

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

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

Annals Of Nuclear Energy. 2023-10-07. Vol. 195, p. 110170. DOI : 10.1016/j.anucene.2023.110170.

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. 

Nuclear Engineering And Design. 2023-07-01. Vol. 408, p. 112320. DOI : 10.1016/j.nucengdes.2023.112320.

Analysis of the preliminary campaign for the PETALE program

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

Epj Nuclear Sciences & Technologies. 2023-06-14. Vol. 9, p. 25. DOI : 10.1051/epjn/2023010.

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

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

Nuclear Engineering And Design. 2023-03-04. Vol. 406, p. 112232. DOI : 10.1016/j.nucengdes.2023.112232.

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

V. A. Di Nora / K. Mikityuk; E. Fridman (Dir.)  

Lausanne, EPFL, 2023. 

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

E. C. Kursun / P. Spätig (Dir.)  

Lausanne, EPFL, 2023. 

Gamma-Blind Fast Neutron Detection for Spent Nuclear Fuel Characterization

A. Wolfertz / A. Pautz; R. E. Adams (Dir.)  

Lausanne, EPFL, 2023. 

Unmoderated molten salt reactors design optimisation for power stability

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

Annals Of Nuclear Energy. 2022-11-01. Vol. 177, p. 109265. DOI : 10.1016/j.anucene.2022.109265.

Towards coupling conventional with high-fidelity fuel behavior analysis tools

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

Progress In Nuclear Energy. 2022-10-01. Vol. 152, p. 104357. DOI : 10.1016/j.pnucene.2022.104357.

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 

Annals Of Nuclear Energy. 2022-06-01. Vol. 170, p. 109011. DOI : 10.1016/j.anucene.2022.109011.

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 

Progress In Nuclear Energy. 2022-04-01. Vol. 146, p. 104148. DOI : 10.1016/j.pnucene.2022.104148.

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 

Annals Of Nuclear Energy. 2022-04-01. Vol. 168, p. 108891. DOI : 10.1016/j.anucene.2021.108891.

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

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

IEEE Transactions on Nuclear Science. 2022-04-01. Vol. 69, num. 4, p. 825-831. DOI : 10.1109/TNS.2022.3143238.

Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors

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

Energies. 2022-02-01. Vol. 15, num. 4, p. 1512. DOI : 10.3390/en15041512.

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 

Nuclear Engineering And Design. 2022-02-01. Vol. 387, p. 111604. DOI : 10.1016/j.nucengdes.2021.111604.

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

M. A. H. M. Sayed / K. Mikityuk; A. Dehbi (Dir.)  

Lausanne, EPFL, 2022. 

Advanced methodologies for modeling and assessment of SFR safety functions

J. Bodi / K. Mikityuk; A. Ponomarev (Dir.)  

Lausanne, EPFL, 2022. 

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

M. A. Veicht / A. Pautz; D. Schumann (Dir.)  

Lausanne, EPFL, 2022. 

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

F. Vitullo / A. Pautz; V. P. Lamirand (Dir.)  

Lausanne, EPFL, 2022. 

Delayed Hydride Cracking in Irradiated and Unirradiated Zircaloy-2 Cladding

A. W. Colldeweih / M. A. Pouchon; J. Bertsch (Dir.)  

Lausanne, EPFL, 2022. 

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

M. Papadionysiou / A. Pautz; M. Hursin (Dir.)  

Lausanne, EPFL, 2022. 

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

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

Annals Of Nuclear Energy. 2022-01-01. Vol. 165, p. 108758. DOI : 10.1016/j.anucene.2021.108758.

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

A. S. A. Shama / A. Pautz; D. Rochman (Dir.)  

Lausanne, EPFL, 2022. 

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

K. W. Wong; L. Bures; K. Mikityuk 

Nuclear Technology. 2022. Vol. 208, num. 8, p. 1266-1278. DOI : 10.1080/00295450.2021.1971025.

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

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

International Journal For Numerical Methods In Engineering. 2022. Vol. 123, num. 2, p. 309-338. DOI : 10.1002/nme.6857.

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. 

European Physical Journal Plus. 2021-12-15. Vol. 137, num. 1, p. 25. DOI : 10.1140/epjp/s13360-021-02230-0.

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

S. Radman; C. Fiorina; A. Pautz 

Nuclear Engineering And Design. 2021-12-01. Vol. 384, p. 111422. DOI : 10.1016/j.nucengdes.2021.111422.

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 

Annals Of Nuclear Energy. 2021-12-01. Vol. 163, p. 108541. DOI : 10.1016/j.anucene.2021.108541.

Delayed gamma fraction determination in the zero power reactor CROCUS

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

Epj Nuclear Sciences & Technologies. 2021-09-23. Vol. 7, p. 16. DOI : 10.1051/epjn/2021015.

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

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

Nuclear Engineering And Technology. 2021-09-01. Vol. 53, num. 9, p. 2816-2829. DOI : 10.1016/j.net.2021.03.013.

Hybrid halide perovskite neutron detectors

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

Scientific Reports. 2021-08-30. Vol. 11, num. 1, p. 17159. DOI : 10.1038/s41598-021-95586-3.

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 

Ieee Transactions On Applied Superconductivity. 2021-08-01. Vol. 31, num. 5, p. 4701105. DOI : 10.1109/TASC.2021.3059602.

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

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

Fluids. 2021-08-01. Vol. 6, num. 8, p. 266. DOI : 10.3390/fluids6080266.

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. 

Progress In Nuclear Energy. 2021-08-01. Vol. 138, p. 103805. DOI : 10.1016/j.pnucene.2021.103805.

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. 

Neural Computing & Applications. 2021-07-04. Vol. 33, p. 16627–16639. DOI : 10.1007/s00521-021-06258-2.

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

L. Bures; Y. Sato; A. Pautz 

Journal Of Computational Physics. 2021-07-01. Vol. 436, p. 110291. DOI : 10.1016/j.jcp.2021.110291.

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 

Annals Of Nuclear Energy. 2021-06-01. Vol. 155, p. 108183. DOI : 10.1016/j.anucene.2021.108183.

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. 

Annals Of Nuclear Energy. 2021-06-01. Vol. 155, p. 108144. DOI : 10.1016/j.anucene.2021.108144.

Investigation on the effect of eccentricity for fuel disc irradiation tests

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

Nuclear Engineering And Technology. 2021-05-01. Vol. 53, num. 5, p. 1602-1611. DOI : 10.1016/j.net.2020.11.003.

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

S. Radman; C. Fiorina; A. Pautz 

Nuclear Engineering and Design. 2021-04-12. Vol. 379, p. 111178. DOI : 10.1016/j.nucengdes.2021.111178.

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 

International Journal Of Fatigue. 2021-04-01. Vol. 145, p. 106111. DOI : 10.1016/j.ijfatigue.2020.106111.

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

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

2021-02-22. PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, Cambridge, United Kingdom, March 29th-April 2nd, 2020. p. 08004. DOI : 10.1051/epjconf/202124708004.

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. 

2021-02-22. PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, Cambridge, United Kingdom, March 29th-April 2nd, 2020. p. 21006. DOI : 10.1051/epjconf/202124721006.

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. 

2021-02-22.  PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future , Cambridge, United Kingdom, March 29th-April 2nd, 2020. p. 04007. DOI : 10.1051/epjconf/202124704007.

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. 

2021-02-22. PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future , Cambridge, United Kingdom, March 29th-April 2nd, 2020. p. 21010. DOI : 10.1051/epjconf/202124721010.

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

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

2021-02-22. PHYSOR 2020: Transition to a Scalable Nuclear Future, Cambridge, United Kingdom, March 29th-April 2nd, 2020. p. 08015. DOI : 10.1051/epjconf/202124708015.

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 

2021-02-22. PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future . p. 08014. DOI : 10.1051/epjconf/202124708014.

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. 

Metals. 2021-02-01. Vol. 11, num. 2, p. 307. DOI : 10.3390/met11020307.

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 

Metals. 2021-02-01. Vol. 11, num. 2, p. 221. DOI : 10.3390/met11020221.

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. 

2021-01-01. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. p. 04029. DOI : 10.1051/epjconf/202125304029.

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. 

2021-01-01. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. p. 04024. DOI : 10.1051/epjconf/202125304024.

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

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

2021-01-01. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. p. 04022. DOI : 10.1051/epjconf/202125304022.

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. 

2021-01-01. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. p. 04023. DOI : 10.1051/epjconf/202125304023.

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. 

2021-01-01. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. p. 04007. DOI : 10.1051/epjconf/202125304007.

Fundamental study on microlayer dynamics in nucleate boiling

L. Bures / A. Pautz; Y. Sato (Dir.)  

Lausanne, EPFL, 2021. 

Improved methodology for analysis and design of Molten Salt Reactors

R. Gonzalez Gonzaga De Oliveira / K. Mikityuk; J. Krepel (Dir.)  

Lausanne, EPFL, 2021. 

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

A. Scolaro / A. Pautz; I. D. Clifford (Dir.)  

Lausanne, EPFL, 2021. 

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

S. Radman / A. Pautz; C. Fiorina (Dir.)  

Lausanne, EPFL, 2021. 

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

E. Vlassopoulos / A. Pautz; S. Caruso (Dir.)  

Lausanne, EPFL, 2021. 

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 

Nuclear Engineering And Design. 2021-01-01. Vol. 371, p. 111010. DOI : 10.1016/j.nucengdes.2020.111010.

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

A. Aures / A. Pautz; W. Zwermann (Dir.)  

Lausanne, EPFL, 2021. 

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

L. Cui / M. A. Pouchon; Y. Dai (Dir.)  

Lausanne, EPFL, 2021. 

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

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

Nuclear Engineering And Design. 2020-12-15. Vol. 370, p. 110897. DOI : 10.1016/j.nucengdes.2020.110897.

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

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

Progress In Nuclear Energy. 2020-12-01. Vol. 130, p. 103551. DOI : 10.1016/j.pnuene.2020.103551.

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. 

Nuclear Engineering And Design. 2020-12-01. Vol. 369, p. 110826. DOI : 10.1016/j.nucengdes.2020.110826.

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 

Journal of Nuclear Engineering. 2020-11-10. Vol. 1, num. 1, p. 54-62. DOI : 10.3390/jne1010005.

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. 

Annals Of Nuclear Energy. 2020-11-01. Vol. 147, p. 107669. DOI : 10.1016/j.anucene.2020.107669.

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. 

European Journal of Mechanics – A/Solids. 2020-10-22. Vol. 85, p. 1-22, 104149. DOI : 10.1016/j.euromechsol.2020.104149.

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

M. J. Veljovic; A. K. Skrivervik 

Ieee Antennas And Wireless Propagation Letters. 2020-10-01. Vol. 19, num. 10, p. 1749-1753. DOI : 10.1109/LAWP.2020.3016340.

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

R. Mouginot; P. Spatig; H-P. Seifert 

Mechanics Of Materials. 2020-10-01. Vol. 149, p. 103541. DOI : 10.1016/j.mechmat.2020.103541.

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

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

2020-09-30.  ND 2019: International Conference on Nuclear Data for Science and Technology . p. 18004. DOI : 10.1051/epjconf/202023918004.

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 

Annals Of Nuclear Energy. 2020-09-01. Vol. 144, p. 107504. DOI : 10.1016/j.anucene.2020.107504.

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

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

Epj Nuclear Sciences & Technologies. 2020-08-28. Vol. 6, p. 52. DOI : 10.1051/epjn/2020015.

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

F. Grimberg 

2020-06-14.

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

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

Annals Of Nuclear Energy. 2020-06-01. Vol. 140, p. 107102. DOI : 10.1016/j.anucene.2019.107102.

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

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

Ieee Transactions On Applied Superconductivity. 2020-06-01. Vol. 30, num. 4, p. 4701505. DOI : 10.1109/TASC.2020.2974423.

Uncertainty propagation based on correlated sampling technique for nuclear data applications

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

Epj Nuclear Sciences & Technologies. 2020-04-08. Vol. 6, p. 8. DOI : 10.1051/epjn/2020003.

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

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

Epj Nuclear Sciences & Technologies. 2020-04-08. Vol. 6, p. 9. DOI : 10.1051/epjn/2020004.

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. 

Ieee Transactions On Nuclear Science. 2020-04-01. Vol. 67, num. 4, p. 625-635. DOI : 10.1109/TNS.2020.2977530.

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

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

Journal Of Nuclear Engineering And Radiation Science. 2020-04-01. Vol. 6, num. 2, p. 021108. DOI : 10.1115/1.4044910.

Treatment of the implicit effect in Shark-X

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

Annals Of Nuclear Energy. 2020-04-01. Vol. 138, p. 107178. DOI : 10.1016/j.anucene.2019.107178.

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

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

Progress In Nuclear Energy. 2020-03-01. Vol. 121, p. 103245. DOI : 10.1016/j.pnucene.2020.103245.

The OFFBEAT multi-dimensional fuel behavior solver

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

Nuclear Engineering And Design. 2020-03-01. Vol. 358, p. 110416. DOI : 10.1016/j.nucengdes.2019.110416.

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 

Annals Of Nuclear Energy. 2020-03-01. Vol. 137, p. 107146. DOI : 10.1016/j.anucene.2019.107146.

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. 

Nuclear Technology. 2020-02-14. Vol. 206, num. 10, p. 1566-1583. DOI : 10.1080/00295450.2019.1701906.

Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

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

European Physical Journal Plus. 2020-02-07. Vol. 135, num. 2, p. 233. DOI : 10.1140/epjp/s13360-020-00258-2.

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. 

2020-01-20. ANIMMA 2019 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications, Portorož (Slovenia), 21-25 June 2021. p. 04020. DOI : 10.1051/epjconf/202022504020.

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. 

2020. 29th International Conference Nuclear Energy for New Europe (NENE 2020), Portorož, Slovenia, September 7–10, 2020. p. 212.1 – 212.8.

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. 

2020-01-01. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. p. 04023. DOI : 10.1051/epjconf/202022504023.

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

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

2020-01-01. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. p. 04021. DOI : 10.1051/epjconf/202022504021.

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

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

2020-01-01. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. p. 04016. DOI : 10.1051/epjconf/202022504016.

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. 

2020-01-01. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. p. 04018. DOI : 10.1051/epjconf/202022504018.

Power calibration methodology at the CROCUS reactor

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

2020-01-01. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. p. 04022. DOI : 10.1051/epjconf/202022504022.

Data assimilation of post irradiation examination experiments to adjust fission yields

D. Siefman; M. Hursin; A. Pautz 

2020-01-01. International Conference on Nuclear Data for Science and Technology (ND), Beijing, PEOPLES R CHINA, May 19-24, 2019. p. 13004. DOI : 10.1051/epjconf/202023913004.

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. 

2020-01-01. International Conference on Nuclear Data for Science and Technology (ND), Beijing, PEOPLES R CHINA, May 19-24, 2019. p. 22001. DOI : 10.1051/epjconf/202023922001.

Adaptive Regularization For Three-Dimensional Optical Diffraction Tomography

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

2020-01-01. IEEE 17th International Symposium on Biomedical Imaging (ISBI), Iowa, IA, Apr 03-07, 2020. p. 182-186. DOI : 10.1109/ISBI45749.2020.9098523.

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

E. Fornasiere / P. Spätig; M. Calviani (Dir.)  

Lausanne, EPFL, 2020. 

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

W. Chen / P. Spätig (Dir.)  

Lausanne, EPFL, 2020. 

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

D. Chionis / A. Pautz; A. Dokhane (Dir.)  

Lausanne, EPFL, 2020. 

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

J. Gao / A. Pautz; B. Auchmann (Dir.)  

Lausanne, EPFL, 2020. 

Experimental and numerical study of stochastic branching noise in nuclear reactors

O. V. Pakari / A. Pautz; V. P. Lamirand (Dir.)  

Lausanne, EPFL, 2020. 

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

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

Annals Of Nuclear Energy. 2020-01-01. Vol. 135, p. 106951. DOI : 10.1016/j.anucene.2019.106951.

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

F. Bostelmann / A. Pautz; W. Zwermann (Dir.)  

Lausanne, EPFL, 2020. 

Reactor simulations with nuclear data uncertainties

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

Nuclear Engineering And Design. 2019-12-15. Vol. 355, p. 110313. DOI : 10.1016/j.nucengdes.2019.110313.

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

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

Nuclear Engineering And Design. 2019-12-15. Vol. 355, p. 110291. DOI : 10.1016/j.nucengdes.2019.110291.

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. 

European Physical Journal Plus. 2019-12-01. Vol. 134, num. 12, p. 614. DOI : 10.1140/epjp/i2019-12942-1.

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

C. Fiorina 

Annals Of Nuclear Energy. 2019-12-01. Vol. 134, p. 376-382. DOI : 10.1016/j.anucene.2019.06.024.

Breed-and-burn fuel cycle in molten salt reactors

B. Hombourger; J. Krepel; A. Pautz 

EPJ Nuclear Sciences & Technologies. 2019-11-15. Vol. 5, p. 15. DOI : 10.1051/epjn/2019026.

Application of multiphysics model order reduction to doppler/neutronic feedback

P. German; J. C. Ragusa; C. Fiorina 

EPJ Nuclear Sciences & Technologies. 2019-11-14. Vol. 5, p. 17. DOI : 10.1051/epjn/2019034.

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 

Annals Of Nuclear Energy. 2019-06-01. Vol. 128, p. 390-397. DOI : 10.1016/j.anucene.2019.01.031.

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. 

Corrosion Science. 2019-05-15. Vol. 152, p. 172-189. DOI : 10.1016/j.corsci.2019.03.013.

Application of causality analysis on nuclear reactor systems

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

Chaos. 2019-04-01. Vol. 29, num. 4, p. 043126. DOI : 10.1063/1.5083905.

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

A. Shama; M. A. Pouchon; I. Clifford 

Additive Manufacturing. 2019-03-01. Vol. 26, p. 1-14. DOI : 10.1016/j.addma.2018.12.011.

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

C. Fiorina 

2019-01-01. 11th Workshop on Open Source Field Operation And Manipulation (OpenFOAM), Guimaraes, PORTUGAL, Jun 26-30, 2016. p. 211-221. DOI : 10.1007/978-3-319-60846-4_16.

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. 

2019. International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019), Portland, OR, USA, August 25-29, 2019.

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. 

2019. International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019), Portland, OR, USA, August 25-29, 2019.

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. 

Annals of Nuclear Energy. 2019. Vol. 136, p. 107034. DOI : 10.1016/j.anucene.2019.107034.

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. 

2019. WONDER 2018 : 5th International Workshop On Nuclear Data Evaluation for Reactor applications, Aix-en-Provence, France, October 8-12, 2018. DOI : 10.1051/epjconf/201921103003.

Development and Application of Data Assimilation Methods in Reactor Physics

D. J. Siefman / A. Pautz; M. Hursin (Dir.)  

Lausanne, EPFL, 2019. 

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

Z. Que / P. Spätig (Dir.)  

Lausanne, EPFL, 2019. 

High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

V. Bykov / A. Pautz; B. Volmert (Dir.)  

Lausanne, EPFL, 2019. 

Extension of the nodal code DYN3D to SFR applications

E. Nikitin / A. Pautz; E. Fridman (Dir.)  

Lausanne, EPFL, 2019. 

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

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

Kerntechnik. 2018-12-01. Vol. 83, num. 6, p. 507-512. DOI : 10.3139/124.110948.

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

R. G. G. de Oliveira; K. Mikityuk 

Annals of Nuclear Energy. 2018-11-01. Vol. 121, p. 446-451. DOI : 10.1016/j.anucene.2018.07.036.

A reduced order accelerator for time-dependent segregated neutronic solvers

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

Annals Of Nuclear Energy. 2018-11-01. Vol. 121, p. 177-185. DOI : 10.1016/j.anucene.2018.07.032.

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

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

European Physical Journal Plus. 2018-10-19. Vol. 133, num. 10, p. 429. DOI : 10.1140/epjp/i2018-12303-8.

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 

Materials Science and Engineering:. 2018-10-01. Vol. A742, p. 842-850. DOI : 10.1016/j.msea.2018.09.107.

Kinetic Parameter Measurements in the CROCUS Reactor Using Current Mode Instrumentation

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

Ieee Transactions On Nuclear Science. 2018-09-01. Vol. 65, num. 9, p. 2456-2460. DOI : 10.1109/TNS.2018.2831180.

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. 

2018. PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, Cancún, Mexico, April 22-26, 2018.

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. 

2018. PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, Cancún, Mexico, April 22-26, 2018.

Testing of a sCVD diamond detection system in the CROCUS reactor

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

The European Physical Journal. 2018. Vol. A54, num. 5, p. 82. DOI : 10.1140/epja/i2018-12519-1.

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

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

2018. WONDER 2018 : 5th International Workshop On Nuclear Data Evaluation for Reactor applications, Aix-en-Provence, France, October 8-12, 2018. DOI : 10.1051/epjconf/201921103002.

Design of Separated Element Reflector Experiments in CROCUS: PETALE

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

2018-01-01. 16th International Symposium on Reactor Dosimetry, Santa Fe, NM, May 07-12, 2017. p. 1-14. DOI : 10.1520/STP760820170090.

Statistical Burnup Distribution Of Moving Pebbles In Htr-Pm Reactor

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

2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V009T16A005. DOI : 10.1115/ICONE26-81082.

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

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

2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V003T02A051. DOI : 10.1115/ICONE26-82381.

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. 

2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V06BT08A062. DOI : 10.1115/ICONE26-82507.

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 

2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V003T02A027. DOI : 10.1115/ICONE26-81574.

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

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

2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V004T15A018. DOI : 10.1115/ICONE26-82260.

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

P. Mala / A. Pautz (Dir.)  

Lausanne, EPFL, 2018. 

Conceptual Design of a Sustainable Waste Burning Molten Salt Reactor

B. A. Hombourger / A. Pautz; J. Krepel (Dir.)  

Lausanne, EPFL, 2018. 

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

S. Knitel / P. Spaetig (Dir.)  

Lausanne, EPFL, 2018. 

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

A. Rais / A. Pautz; M. Hursin (Dir.)  

Lausanne, EPFL, 2018. 

Characterisation of the activation in Crocus

V. Chaussonnet 

2018-01-01.

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 

2018. PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, Cancun, Mexico, April, 2018.

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

D. C. Wicaksono / A. Pautz; O. Zerkak (Dir.)  

Lausanne, EPFL, 2018. 

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

I. Villacampa Roses / P. Spätig; J-C. Chen (Dir.)  

Lausanne, EPFL, 2018. 

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

A. Theler 

2017-08-25.

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

I. Tanseri 

2017-06-28.

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

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

Theoretical and Applied Fracture Mechanics. 2017-05-26. Vol. 90, p. 244-250. DOI : 10.1016/j.tafmec.2017.05.023.

Design of Separated Element Reflector Experiments in CROCUS: PETALE

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

2017-05-07. ISRD16 International Symposium on Reactor Dosimetry, Santa Fe, New Mexico, USA, May 7-12, 2017.

Concrete and Metallic Structures Activation Calculations

H. Gavotto 

2017-01-13.

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

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

2017. M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, April 16-20, 2017.

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

V. V. Brankov / A. Pautz; K. Mikityuk (Dir.)  

Lausanne, EPFL, 2017. 

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 

Progress in Nuclear Energy. 2017. Vol. 101C, p. 280-287. DOI : 10.1016/j.pnucene.2017.03.018.

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

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

2017. M&C 2017 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, South Korea, April 16-20, 2017.

Development of Current and Fast Neutron Noise Measurements in CROCUS

O. V. Pakari 

2016-08-18.

Development of an experimental channel in CROCUS

A. Theler 

2016-01-05.

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 

Nuclear Materials and Energy. 2016. Vol. 9, p. 311-316. DOI : 10.1016/j.nme.2016.06.017.

Future experimental programmes in the CROCUS reactor

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

2016. RRFM/IGORR 2016, Berlin, Germany, March 13-17, 2016. p. 284-292. DOI : 10.13140/RG.2.1.2309.6728.

Neutron noise measurement in current mode

O. V. Pakari 

2015-12-22.

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 

Annals of Nuclear Energy. 2015. Vol. 85, p. 434-443. 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

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

Science and Technology of Nuclear Installations. 2015. Vol. 2015, p. 237646. DOI : 10.1155/2015/237646.

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

D. J. Siefman 

2015.

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

K. Wang / P. Spätig; Y. Dai (Dir.)  

Lausanne, EPFL, 2015. 

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

D. C. Wicaksono; O. Zerkak; A. Pautz 

2015. 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-16), Chicago, Illinois, USA, September 30 – October 4, 2015.

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

T. Zhu / A. Pautz; A. Vasiliev (Dir.)  

Lausanne, EPFL, 2015. 

Verification of a reactor physics calculation scheme for the CROCUS reactor

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

2014. 3rd International Technical Meeting on Small Reactors, Ottawa, Canada, November 5-7, 2014.

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. 

Nuclear Data Sheets. 2014. Vol. 118, p. 498-501. DOI : 10.1016/j.nds.2014.04.117.

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 

Nuclear Data Sheets. 2014. Vol. 118, p. 453-455. DOI : 10.1016/j.nds.2014.04.104.

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. 

Nuclear Data Sheets. 2014. Vol. 118, p. 388-391. DOI : 10.1016/j.nds.2014.04.088.

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

D. C. Wicaksono; O. Zerkak; A. Pautz 

2014. The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, December 14-18, 2014.

Sensitivity Analysis of a Bottom Reflood Simulation using Morris Screening Method

D. C. Wicaksono; O. Zerkak; A. Pautz 

2014. The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, December 14-18, 2014.

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. 

Nuclear Instruments & Methods In Physics Research Section B-Beam Interactions With Materials And Atoms. 2014. Vol. 336, p. 143-148. DOI : 10.1016/j.nimb.2014.04.026.

Validation of Two Monte Carlo Codes for LWR Burnup Calculations

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

2014. PHYSOR 2014 International Conference, The Westin Miyako, Kyoto, Japan, September 28 – October 3, 2014.

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 

2013. American-Nuclear-Society (ANS) International Conference on the Physics of Reactors (PHYSOR), Knoxville, TN, APR 15-20, 2012. p. 292-307.

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 

2013. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2013), Sun Valley, Idaho, USA, May 5-9, 2013.

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 

Nuclear Technology. 2013. Vol. 183, num. 3, p. 484-503. DOI : 10.13182/NT13-A19436.

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 

Nuclear Instruments & Methods In Physics Research Section A-Accelerators Spectrometers Detectors And Associated Equipment. 2013. Vol. 698, p. 72-80. DOI : 10.1016/j.nima.2012.09.008.

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 

Annals Of Nuclear Energy. 2012. Vol. 49, p. 191-199. DOI : 10.1016/j.anucene.2012.05.035.

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 

Annals Of Nuclear Energy. 2012. Vol. 49, p. 182-190. DOI : 10.1016/j.anucene.2012.05.036.

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

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

Nuclear Instruments & Methods In Physics Research Section A-Accelerators Spectrometers Detectors And Associated Equipment. 2012. Vol. 693, p. 59-66. DOI : 10.1016/j.nima.2012.07.009.

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

K. Sun / R. Chawla (Dir.)  

Lausanne, EPFL, 2012. 

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 

Nuclear Engineering And Design. 2012. Vol. 247, p. 236-247. DOI : 10.1016/j.nucengdes.2012.02.011.

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

A. Marinoni; G. Girardin; K. Mikityuk 

Annals Of Nuclear Energy. 2012. Vol. 44, p. 26-33. DOI : 10.1016/j.anucene.2012.01.011.

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 

Nuclear Engineering And Design. 2012. Vol. 242, p. 267-284. DOI : 10.1016/j.nucengdes.2011.10.011.

Neutronics Experiments and Analysis Related to Strong Moderation Heterogeneity in LWRs

D. Rätz / R. Chawla (Dir.)  

Lausanne, EPFL, 2012. 

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

F. D. Giust / R. Chawla (Dir.)  

Lausanne, EPFL, 2012. 

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

F. D. Giust; P. Grimm; R. Chawla 

Journal Of Engineering For Gas Turbines And Power-Transactions Of The Asme. 2011. Vol. 133, num. 5, p. 052909. DOI : 10.1115/1.4002823.

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

P. Vinai; R. Macian-Juan; R. Chawla 

Annals Of Nuclear Energy. 2011. Vol. 38, p. 358-370. DOI : 10.1016/j.anucene.2010.10.007.

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

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

Nuclear Engineering And Design. 2011. Vol. 241, p. 245-256. DOI : 10.1016/j.nucengdes.2010.10.021.

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 

Annals Of Nuclear Energy. 2011. Vol. 38, p. 794-801. DOI : 10.1016/j.anucene.2010.11.021.

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

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

Annals Of Nuclear Energy. 2011. Vol. 38, p. 1645-1657. DOI : 10.1016/j.anucene.2011.02.018.

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

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

Annals Of Nuclear Energy. 2011. Vol. 38, p. 1842-1851. DOI : 10.1016/j.anucene.2011.05.017.

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 

Annals Of Nuclear Energy. 2011. Vol. 38, p. 2319-2332. DOI : 10.1016/j.anucene.2011.07.007.

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

A. Chenu; K. Mikityuk; R. Chawla 

Nuclear Engineering And Design. 2011. Vol. 241, p. 3898-3909. DOI : 10.1016/j.nucengdes.2011.07.009.

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

D. Bertolotto / R. Chawla (Dir.)  

Lausanne, EPFL, 2011. 

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

A. Chenu / R. Chawla (Dir.)  

Lausanne, EPFL, 2011. 

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

H. Kröhnert / R. Chawla (Dir.)  

Lausanne, EPFL, 2011. 

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 

Annals Of Nuclear Energy. 2010. Vol. 37, p. 1629-1639. DOI : 10.1016/j.anucene.2010.08.006.

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 

2010. 4th International Topical Meeting on High Temperature Reactor Technology, Washington, DC, Sep 28-Oct 01, 2008. p. 3115-3125. DOI : 10.1016/j.nucengdes.2010.05.030.

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 

Nuclear Instruments & Methods In Physics Research Section A-Accelerators Spectrometers Detectors And Associated Equipment. 2010. Vol. 624, p. 101-108. DOI : 10.1016/j.nima.2010.09.033.

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

A. Epiney; K. Mikityuk; R. Chawla 

Annals Of Nuclear Energy. 2010. Vol. 37, p. 875-887. DOI : 10.1016/j.anucene.2010.01.020.

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

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

Journal of Engineering for Gas Turbines and Power. 2010. Vol. 132, num. 10, p. 1-7. DOI : 10.1115/1.4000336.

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

A. S. Epiney / R. Chawla (Dir.)  

Lausanne, EPFL, 2010. 

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. 

Annals of Nuclear Energy. 2009. Vol. 36, num. 10, p. 1536-43. DOI : 10.1016/j.anucene.2009.07.012.

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. 

Journal of Nuclear Science and Technology. 2009. Vol. 46, num. 9, p. 933-43. DOI : 10.3327/jnst.46.933.

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

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

Annals of Nuclear Energy. 2009. Vol. 36, num. 8, p. 1262-9. DOI : 10.1016/j.anucene.2009.01.015.

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. 

Nuclear Science and Engineering. 2009. Vol. 163, num. 1, p. 17-25. DOI : 10.13182/NSE08-55.

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 

Annals of Nuclear Energy. 2009. Vol. 36, num. 6, p. 853-8. DOI : 10.1016/j.anucene.2009.02.013.

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

H. Ferroukhi; O. Zerkak; R. Chawla 

Annals of Nuclear Energy. 2009. Vol. 36, num. 8, p. 1184-200. DOI : 10.1016/j.anucene.2009.04.006.

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 

Annals of Nuclear Energy. 2009. Vol. 36, num. 3, p. 286-291. DOI : 10.1016/j.anucene.2008.12.010.

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

A. Chenu; K. Mikityuk; R. Chawla 

Nuclear Engineering and Design. 2009. Vol. 239, num. 11, p. 2417-29. DOI : 10.1016/j.nucengdes.2009.07.015.

Editorial

R. Chawla 

Annals of Nuclear Energy. 2009. Vol. 36, num. 3, p. 255-257. DOI : 10.1016/j.anucene.2008.11.008.

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 

Nuclear Engineering and Design. 2009. Vol. 239, num. 7, p. 1220-8. DOI : 10.1016/j.nucengdes.2009.02.019.

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 

Annals of Nuclear Energy. 2009. Vol. 36, num. 3, p. 310-16. DOI : 10.1016/j.anucene.2008.11.027.

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

G. Girardin / R. Chawla (Dir.)  

Lausanne, EPFL, 2009. 

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

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

2008. European Workshop on Neutron Optics (NOP 07), Villigen, SWITZERLAND, Mar 05-07, 2007. p. 59-63. DOI : 10.1016/j.nima.2007.11.061.

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 

Annals of Nuclear Energy. 2008. Vol. 35, num. 12, p. 2432-5. DOI : 10.1016/j.anucene.2008.07.009.

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 

Annals of Nuclear Energy. 2008. Vol. 35, num. 4, p. 565-9. DOI : 10.1016/j.anucene.2007.08.018.

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 

Annals of Nuclear Energy. 2008. Vol. 35, num. 3, p. 478-84. DOI : 10.1016/j.anucene.2007.06.025.

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. 

Annals of Nuclear Energy. 2008. Vol. 35, num. 11, p. 2042-50. DOI : 10.1016/j.anucene.2008.06.001.

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. 

Annals of Nuclear Energy. 2008. Vol. 35, num. 12, p. 2206-18. DOI : 10.1016/j.anucene.2008.09.008.

Management of actinide waste inventories in nuclear phase-out scenarios

M. Cometto; P. Wydler; R. Chawla 

Annals of Nuclear Energy. 2008. Vol. 35, num. 8, p. 1447-1460. DOI : 10.1016/j.anucene.2008.01.016.

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

R. Chawla; F. Jatuff; F. Tani 

Annals of Nuclear Energy. 2008. Vol. 35, num. 3, p. 495-502. 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

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

Journal of Nuclear Science and Technology. 2008. Vol. 45, num. 8, p. 828-835. DOI : 10.3327/jnst.45.828.

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 

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2008. Vol. 589, num. 3, p. 425-35. DOI : 10.1016/j.nima.2008.03.005.

Interpretation of high-burnup fuel annealing tests

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

Journal of Nuclear Science and Technology. 2008. Vol. 45, num. 7, p. 639-646. DOI : 10.3327/jnst.45.639.

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

P. Petkevich / R. Chawla (Dir.)  

Lausanne, EPFL, 2008. 

Modelling of fission gas behaviour in high burnup nuclear fuel

P. Blair / R. Chawla (Dir.)  

Lausanne, EPFL, 2008. 

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

P. Vinai; R. Macian-Juan; R. Chawla 

Annals of Nuclear Energy. 2007. Vol. 34, num. 8, p. 628-40. DOI : 10.1016/j.anucene.2007.03.003.

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 

Annals of Nuclear Energy. 2007. Vol. 34, num. 8, p. 615-27. DOI : 10.1016/j.anucene.2007.02.020.

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

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

Annals of Nuclear Energy. 2007. Vol. 34, num. 9, p. 707-18. DOI : 10.1016/j.anucene.2007.03.009.

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 

Nuclear Technology. 2007. Vol. 157, num. 1, p. 18-36. DOI : 10.13182/NT07-A3799.

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. 

Nuclear Science and Engineering. 2007. Vol. 155, num. 1, p. 96-101. DOI : 10.13182/NSE07-A2647.

Statistical uncertainty analysis applied to fuel depletion calculations

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

Journal of Nuclear Science and Technology. 2007. Vol. 44, num. 6, p. 875-885. DOI : 10.3327/jnst.44.875.

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 

Annals of Nuclear Energy. 2007. Vol. 34, num. 1-2, p. 28-35. DOI : 10.1016/j.anucene.2006.11.009.

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

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

Nuclear Science and Engineering. 2007. Vol. 156, num. 1, p. 86-95. DOI : 10.13182/NSE07-A2687.

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 

Annals of Nuclear Energy. 2007. Vol. 34, num. 10, p. 792-802. DOI : 10.1016/j.anucene.2007.04.003.

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 

Annals of Nuclear Energy. 2007. Vol. 34, num. 4, p. 271-87. DOI : 10.1016/j.anucene.2006.12.005.

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

P. Vinai / R. Chawla (Dir.)  

Lausanne, EPFL, 2007. 

Characterisation of high-burnup LWR fuel rods through gamma tomography

S. Caruso / R. Chawla (Dir.)  

Lausanne, EPFL, 2007. 

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 

Medical Physics. 2006. Vol. 33, num. 6, p. 1532-9. DOI : 10.1118/1.2198168.

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. 

Nuclear Physics A. 2006. Vol. 764, p. 1-14. DOI : 10.1016/j.nuclphysa.2005.08.023.

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 

Nuclear Engineering and Design. 2006. Vol. 236, num. 3, p. 284-94. DOI : 10.1016/j.nucengdes.2005.08.007.

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. 

Journal of Nuclear Science and Technology. 2006. Vol. 43, num. 11, p. 1298-1310. DOI : 10.3327/jnst.43.1298.

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

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

Journal of ASTM International. 2006. Vol. 3, num. 3. DOI : 10.1520/JAI13443.

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. 

Annals of Nuclear Energy. 2006. Vol. 33, num. 9, p. 760-5. DOI : 10.1016/j.anucene.2006.04.003.

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

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

Nuclear Engineering and Design. 2006. Vol. 236, num. 23, p. 2452-73. DOI : 10.1016/j.nucengdes.2006.03.012.

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. 

Nuclear Instruments & Methods in Physics Research, Section A (Accelerators, Spectrometers, Detectors and Associated Equipment). 2006. Vol. 562, num. 1, p. 393-400. DOI : 10.1016/j.nima.2006.03.004.

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 

Annals of Nuclear Energy. 2006. Vol. 33, num. 6, p. 490-8. DOI : 10.1016/j.anucene.2006.02.005.

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

F. Jatuff; K. Macku; R. Chawla 

Annals of Nuclear Energy. 2006. Vol. 33, num. 2, p. 198-207. DOI : 10.1016/j.anucene.2005.09.006.

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 

Annals of Nuclear Energy. 2006. Vol. 33, num. 2, p. 119-25. DOI : 10.1016/j.anucene.2005.09.007.

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. 

Journal of Nuclear Science and Technology. 2006. Vol. 43, num. 3, p. 223-230. DOI : 10.3327/jnst.43.223.

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. 

Annals of Nuclear Energy. 2006. Vol. 33, num. 8, p. 739-48. DOI : 10.1016/j.anucene.2005.09.012.

Calculations on fission gas behaviour in the high burnup structure

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

Journal of Nuclear Materials. 2006. Vol. 350, num. 3, p. 232-9. DOI : 10.1016/j.jnucmat.2006.01.006.

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

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

Nuclear Instruments & Methods in Physics Research, Section A (Accelerators, Spectrometers, Detectors and Associated Equipment). 2006. Vol. 556, num. 1, p. 331-8. DOI : 10.1016/j.nima.2005.08.110.

Decomposition analysis of reactivity effect predictions for modern LWR fuel

F. Tani / R. Chawla (Dir.)  

Lausanne, EPFL, 2006. 

144Ce as a potential candidate for interstitial and intravascular brachytherapy

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

International Journal of Radiation Oncology Biology Physics. 2005. Vol. 62, num. 2, p. 585-94. DOI : 10.1016/j.ijrobp.2005.02.005.

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

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

Annals of Nuclear Energy. 2005. Vol. 32, num. 8, p. 843-56. DOI : 10.1016/j.anucene.2005.01.001.

Investigation of ADS-Type heterogeneities in the MUSE4 critical configuration

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

Journal of Nuclear Science and Technology. 2005. Vol. 42, num. 9, p. 779-787. DOI : 10.3327/jnst.42.779.

Calculation of multiple-scattering angular distributions of electrons and positrons

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

Radiation Physics and Chemistry. 2005. Vol. 74, num. 5, p. 264-281. DOI : 10.1016/j.radphyschem.2005.07.006.

FAST: An advanced code system for fast reactor transient analysis

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

Annals of Nuclear Energy. 2005. Vol. 32, num. 15, p. 1613-31. DOI : 10.1016/j.anucene.2005.06.002.

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

K. Mikityuk; P. Coddington; R. Chawla 

Journal of Nuclear Science and Technology. 2005. Vol. 42, num. 7, p. 600-607. DOI : 10.3327/jnst.42.600.

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. 

Transactions of the American Nuclear Society. 2005. Vol. 93, p. 667-8.

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 

Nuclear Science and Engineering. 2005. Vol. 150, num. 1, p. 27-36. DOI : 10.13182/NSE05-A2499.

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

C. E. Negreanu / R. Chawla (Dir.)  

Lausanne, EPFL, 2005. 

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

V. O. Zilio / R. Chawla (Dir.)  

Lausanne, EPFL, 2005. 

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

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

Annals of Nuclear Energy. 2004. Vol. 31, num. 15, p. 1735-63. DOI : 10.1016/j.anucene.2004.05.001.

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

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

Nuclear Science and Engineering. 2004. Vol. 148, num. 1, p. 162-171. DOI : 10.13182/NSE04-A2448.

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 

Nuclear Instruments & Methods in Physics Research, Section A (Accelerators, Spectrometers, Detectors and Associated Equipment). 2004. Vol. 522, num. 3, p. 579-90. DOI : 10.1016/j.nima.2003.12.001.

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

O. Koberl; R. Seiler; R. Chawla 

Nuclear Science and Engineering. 2004. Vol. 146, num. 1, p. 1-12. DOI : 10.13182/NSE04-A2391.

Plutonium management in the medium term

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

Nuclear Technology. 2004. Vol. 148, num. 3, p. 244-258. DOI : 10.13182/NT04-A3564.

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

M. Cometto; P. Wydler; R. Chawla 

Annals of Nuclear Energy. 2004. Vol. 31, num. 4, p. 413-29. DOI : 10.1016/j.anucene.2003.07.001.

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

M. Plaschy / R. Chawla (Dir.)  

Lausanne, EPFL, 2004. 

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

A. Dokhane / R. Chawla (Dir.)  

Lausanne, EPFL, 2004. 

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 

Journal of Nuclear Science and Technology. 2003. Vol. 40, num. 6, p. 429-432. DOI : 10.3327/jnst.40.429.

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

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

Australasian Physical and Engineering Sciences in Medicine. 2003. Vol. 26, num. 2, p. 63-69. DOI : 10.1007/BF03178459.

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

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

Annals of Nuclear Energy. 2003. Vol. 30, num. 17, p. 1731-55. DOI : 10.1016/S0306-4549(03)00136-1.

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. 

Annals of Nuclear Energy. 2003. Vol. 30, num. 8, p. 911-30. DOI : 10.1016/S0306-4549(02)00144-5.

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. 

Annals of Nuclear Energy. 2003. Vol. 30, num. 3, p. 287-99. DOI : 10.1016/S0306-4549(02)00059-2.

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

M. Cometto / R. Chawla (Dir.)  

Lausanne, EPFL, 2003. 

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

C. Pralong / R. Chawla (Dir.)  

Lausanne, EPFL, 2003. 

Assessment of reactivity effects due to localized perturbations in BWR lattices

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

Nuclear Science and Engineering. 2002. Vol. 142, num. 1, p. 96-106. DOI : 10.13182/NSE02-A2291.

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. 

Nuclear Science and Engineering. 2002. Vol. 141, num. 1, p. 32-45. DOI : 10.13182/NSE02-A2264.

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 

Journal of Nuclear Science and Technology. 2002. Vol. 39, num. 9, p. 972-985. DOI : 10.3327/jnst.39.972.

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. 

Progress in Nuclear Energy. 2001. Vol. 38, num. 3-4, p. 335-342. DOI : 10.1016/S0149-1970(00)00130-X.

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

A. Luthi; R. Chawla; G. Rimpault 

Nuclear Science and Engineering. 2001. Vol. 138, num. 3, p. 233-255. DOI : 10.13182/NSE01-A2211.

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. 

Annals of Nuclear Energy. 2001. Vol. 28, num. 7, p. 701-13. DOI : 10.1016/S0306-4549(00)00079-7.

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. 

Nuclear Science and Engineering. 2001. Vol. 139, num. 3, p. 262-272. DOI : 10.13182/NSE01-A2236.

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

R. Chawla; R. J. M. Konings 

Progress in Nuclear Energy. 2001. Vol. 38, num. 3-4, p. 455-458. DOI : 10.1016/S0149-1970(00)00157-8.

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. 

Progress in Nuclear Energy. 2001. Vol. 38, num. 3-4, p. 359-362. DOI : 10.1016/S0149-1970(00)00135-9.

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. 

Progress in Nuclear Energy. 2001. Vol. 38, num. 3-4, p. 351-354. DOI : 10.1016/S0149-1970(00)00133-5.

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

T. Sengstag / R. Chawla (Dir.)  

Lausanne, EPFL, 2001. 

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

M. Rosselet; R. Chawla; T. Williams 

Nuclear Science and Engineering. 2000. Vol. 135, num. 1, p. 33-47. DOI : 10.13182/NSE99-33.

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. 

Nuclear Technology. 2000. Vol. 130, num. 2, p. 159-176. DOI : 10.13182/NT00-A3084.

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

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

Radiation Protection Dosimetry. 2000. Vol. 92, num. 4, p. 313-318. DOI : 10.1093/oxfordjournals.rpd.a033298.

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. 

Annals of Nuclear Energy. 1999. Vol. 26, num. 2, p. 141-8. DOI : 10.1016/S0306-4549(98)89001-4.

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 

Journal of Nuclear Materials. 1999. Vol. 274, num. 1, p. 146-152. DOI : 10.1016/S0022-3115(99)00082-3.

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

M. Rosselet; R. Chawla; T. Williams 

Annals of Nuclear Energy. 1999. Vol. 26, num. 1, p. 75-82. DOI : 10.1016/S0306-4549(98)80001-7.

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. 

Journal of Nuclear Materials. 1999. Vol. 274, num. 1, p. 120-126. DOI : 10.1016/S0022-3115(99)00086-0.

Reactivity measurements and their interpretation in systems with large spatial effects

M. Rosselet / R. Chawla (Dir.)  

Lausanne, EPFL, 1999. 

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

A. Lüthi / R. Chawla (Dir.)  

Lausanne, EPFL, 1999. 

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

M. Rosselet; T. Williams; R. Chawla 

Annals of Nuclear Energy. 1998. Vol. 25, num. 4-5, p. 285-94. DOI : 10.1016/S0306-4549(97)00059-5.

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 

Kerntechnik. 1998. Vol. 63, num. 5-6, p. 239-48.

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

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

Nuclear Technology. 1998. Vol. 122, num. 1, p. 52-63. DOI : 10.13182/NT98-A2850.

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

O. Koeberl / R. Chawla (Dir.)  

Lausanne, EPFL, 1998. 

Konzeption eines uranfreien LWR-Kerns zur Plutoniumverbrennung

U. Kasemeyer / R. Chawla (Dir.)  

Lausanne, EPFL, 1998. 

On the physics feasibility of LWR plutonium fuels without uranium

J. M. Paratte; R. Chawla 

Annals of Nuclear Energy. 1995. Vol. 22, num. 7, p. 471-81. DOI : 10.1016/0306-4549(94)00061-I.

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

R. Chawla; S. L. Bhattacharya 

Wear. 1977. Vol. 43, num. 2, p. 175-183. DOI : 10.1016/0043-1648(77)90112-0.