STARS Publications - Conference Proceedings

2017

Y. Aounallah
Post-Dryout Heat Transfer Assessment of TRACE
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017

Y. Aounallah
TRACE/S3K Code Coupling Simulations of a BWR/4 Anticipated Transient Without Scram
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017

Y. Aounallah
Simulations with TRACE of a BWR/4 Steam Line Break under Hot Standby Conditions
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017

D. Chionis, A. Dokhane, L. Belblidia, M. Pecchia, G. Girardin, H. Ferroukhi, A. Pautz
SIMULATE-3K Analyses of Neutron Noise Response to Fuel Assembly Vibrations and Thermal-Hydraulics Parameters Fluctuations
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017

P. Mala, A. Pautz, S. Canepa, H. Ferroukhi
Nodal and Pin-by-pin Calculations Comparison with Codes SIMULATE-5 and DYN3D
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017

D. Rochman, P. Mala, H. Ferroukhi, A. Vasiliev, M. Seidl, D. Janin, J. Li
Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017

A. Dokhane, G. Grandi, O. Leray, D. Rochman, A. Vasiliev, H. Ferroukhi
Nuclear Data Uncertainty Decomposition for SPERT-III RIA Experiments using SIMULATE-3K and SHARK-X
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017

2016

Y. Aounallah
Simulations of Level-Swell Experiments with TRACE
Proc. Int. Conf. NUTHOS-11, Gyeongju, Korea, October 9-13, 2016

I. Clifford, O. Zerkak, A. Pautz
System Code Validation Series based on a Consistent Plant Nodalisation of the ROSA/LSTF Integral Test Facility using TRACE v5.0 Patch 4
Proc. Int. Conf. NUTHOS-11, Gyeongju, Korea, October 9-13, 2016

R. Mukin, O. Zerkak, A. Pautz
Modeling and Analysis of selected OECD PKL3 Station-Blackout Experiments using TRACE
Proc. Int. Conf. NUTHOS-11, Gyeongju, Korea, October 9-13, 2016

R. Puragliesi, O. Zerkak, A. Pautz
Influence of URANS Turbulence Models on In-Vessel Flow Mixing During Cold Leg Accumulator Injection
Proc. Int. Conf. NUTHOS-11, Gyeongju, Korea, October 9-13, 2016

D. Wicaksono, O. Zerkak, A. Pautz
Bayesian Calibration of Thermal-Hydraulics Model with Time-Dependent Output
Proc. Int. Conf. NUTHOS-11, Gyeongju, Korea, October 9-13, 2016

S. Rahman, D.R. Karanki, D. Wicaksono, O. Zerkak, V.N. Dang
Evaluation of Deterministic Sampling for Uncertainty Quantification in a Probabilistic Accident Analysis Model
Proc. Int. Conf. NUTHOS-11, Gyeongju, Korea, October 9-13, 2016

D. Rochman, A.J. Koning, J.Ch. Sublet, M. Fleming, E. Bauge, S. Hilaire, P. Romain, B. Morillon, H. Duarte, S. Goriely, S.C. van der Marck, H. Sjöstrand, S. Pomp, N. Dzysiuk, O. Cabellos, H. Ferroukhi, A. Vasiliev
The TENDL library: hope, reality and future
Proc. Int. Conf. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016

J.J. Herrero, D. Rochman, O. Leray, A. Vasiliev, M. Pecchia, H. Ferroukhi, S. Caruso
Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
Proc. Int. Conf. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016

M. Hursin, O. Leray, G.Perret, A.Pautz, F. Bostelmann, A. Aures, W. Zwermann
Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
Proc. Int. Conf. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016

O. Leray, D. Rochman, M. Fleming, J-C. Sublet, A. Koning, A. Vasiliev, H. Ferroukhi
Fission yield covariances for JEFF: a Bayesian Monte Carlo method
Proc. Int. Conf. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016

C. Cozzo, A. Epiney, S. Canepa, H. Ferroukhi, O. Zerkak, G. Khvostov,V. Brankov, A. Gorzel
Full Core LOCA Analysis for BWR/6 - Methodology and First Results
Proc. Int. Conf. TopFuel 2016, Boise, Idaho, USA, September 11-16, 2016

O. Leray, L. Fiorito, D. Rochman, H. Ferroukhi, A. Pautz, A. Stankovskiy, G. Van den Eynde
Comparison of Fission Yield Perturbation Methodologies on Nuclide Composition for a PWR UO2 Fuel Assembly
Proc. Int. Conf. PHYSOR 2016, Sun Valley, Idaho, USA, May 1-5, 2016

A. Dokhane, O. Leray, D. Rochman, H. Ferroukhi, A. Pautz
Validation of SIMULATE-3K against SPERT-III Ria Experiments with Quantification of Nuclear Data Uncertainties
Proc. Int. Conf.PHYSOR 2016, Sun Valley, Idaho, USA, May 1-5, 2016

V. Bykov, A. Vasiliev, H. Ferroukhi, A. Pautz
Solution of the Beavrs Benchmark using CASMO-5 / SIMULATE-5 Code Sequence
Proc. Int. Conf.PHYSOR 2016, Sun Valley, Idaho, USA, May 1-5, 2016

D. Chionis, A. Dokhane, H. Ferroukhi, A. Pautz
On Causality Analysis of Nuclear Reactor Noise using Partial Directed Coherence
Proc. Int. Conf.PHYSOR 2016, Sun Valley, Idaho, USA, May 1-5, 2016

S. Canepa, H. Ferroukhi, R. Min, H.G. Joo
COMPARATIVE STUDY OF CASMO-5/SIMULATE-5 AND nTRACER FOR EPR CORE ANALYSES
Proc. Int. Conf.ICAPP 2016, San Francisco, CA, USA, April 17-20, 2016

J. Li, D. Rochman, J. Herrero, H. Ferroukhi, A. Vasiliev, A. Pautz
Towards Analysis of the Bowing E ect on Burnt Nuclear Fuel Compositions Using SERPENT
Proc. American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, USA, March 31-April 3, 2016

R. Savelli, A. Vasiliev, H. Ferroukhi, A. Pautz
Extension of PSI Fast Neutron Fluence (FNF) Modeling Methodology Validation using BWR Dosimetry Data
Proc. American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, USA, March 31-April 3, 2016

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2015

M. Pecchia, J. J. Herrero, H. Ferroukhi, A. Vasiliev, S. Canepa, A. Pautz
COMPLINK: A Versatile Tool for Automatizing the Representation of Material Data in MCNP Models
Proc. Int. Conf. Nuclear Criticality Safety, ICNC 2015, Charlotte, NC, USA, September 13-17, 2015

A. Vasiliev, D. Rochman, T. Zhu, M. Pecchia, H. Ferroukhi, A. Pautz
Towards Application of Neutron Cross-Section Uncertainty Propagation Capability in the Criticality Safety Methodology
Proc. Int. Conf. Nuclear Criticality Safety, ICNC 2015, Charlotte, NC, USA, September 13-17, 2015

J.J. Herrero, M. Pecchia, H. Ferroukhi, S. Canepa, A. Vasiliev, S. Caruso
Computational Scheme for Burnup Credit applied to Long Term Waste Disposal
Proc. Int. Conf. Nuclear Criticality Safety, ICNC 2015, Charlotte, NC, USA, September 13-17, 2015

V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Modeling of Axial Distribution of Released Fission Gas in KKL BWR Fuel Rods during Base Irradiation
Proc. Water Reactor Fuel Performance Meetig TopFuel 2015, Zurich, Switzerland, September 13-17, 2015

A. Dokhane, O. Zerkak, H. Ferroukhi, I. Gajev, J. Judd, T. Kozlowski
TRACE/SIMULATE-3K Analysis of the NEA/OECD Oskarshamn-2 Stability Benchmark
Proc. Int. Top. Meetg.Nucl. Reactor Thermal-Hydraulics NURETH-16, Chicago, USA, August 30 - September 4, 2015

A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Towards a Consolidated Approach for the Validation of Plant System Codes and Models: A Case Study for a BWR Fast Depressurization Event
Proc. Int. Top. Meetg.Nucl. Reactor Thermal-Hydraulics NURETH-16, Chicago, USA, August 30 - September 4, 2015

O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz, H.Perrier
Development, Verification and Test Application of a Hybrid CASMO-5/SERPENT Depletion Scheme
Proc. Joint Int. Conf. on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method, M&C+SNA+MC 2015, Tennessee, USA, April 19-23, 2015

P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Preparation of Pin-By-Pin Nuclear Libraries with Superhomogenization Method for Ntracer and Dort Core Calculations
Proc. Joint Int. Conf. on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method, M&C+SNA+MC 2015, Tennessee, USA, April 19-23, 2015

M. Hursin, L. Rossinelli, H. Ferroukhi and A. Pautz
BWR Full Core Analysis with SERPENT/SIMULATE-3 Hybrid Stochastic/Determinstic Code Sequence
Proc. Joint Int. Conf. on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method, M&C+SNA+MC 2015, Tennessee, USA, April 19-23, 2015

S. Canepa, M. Krack, H. Ferroukhi, A. Pautz
Scalability Benchmarking Methodology for Hybrid Parallel Core Calculations with the Code nTRACER
Proc. Joint Int. Conf. on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method, M&C+SNA+MC 2015, Tennessee, USA, April 19-23, 2015

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2014

Y. Aounallah
Assessment of TRACE against Single-Tube Post-Dryout Heat Transfer Experiments
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

I. Clifford, O. Zerkak, A. Pautz
Post-test Analysis of OECD/NEA ROSA-2 Test 4 using TRACE
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

A. Epiney, O. Zerkak, A. Pautz
Uncertainty and Sensitivity Analysis of COBRA-TF for the Simulation of Selected OECD/NRC BFBT Void Experiments
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

R. Puragliesi, O. Zerkak and A. Pautz
Assessment of CFD URANS Models for Buoyancy Driven Mixing Flows Based on ROCOM Experiments
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

S. Rahman, D.R. Karanki, O. Zerkak, V.N. Dang
Treatment of Epistemic and Aleatory Uncertainties in DET Simulations: Computational Framework with ADS-TRACE
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

D. Wicaksono,O. Zerkak, A. Pautz
Exploring Variability in Reflood Simulation Results: An Application of Functional Data Analysis
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

D. Wicaksono,O. Zerkak, A. Pautz
Sensitivity Analysis of a Bottom Reflood Simulation using the Morris Screening Method
Proc. Int. Conf. Nucl. Thermal-Hydraulics NUTHOS-10, Okinawa, Japan, December 14 - 18, 2014

A. Dokhane, H. Ferroukhi, A. Pautz
Analysis of the OECD/NEA Oskarshamn-2 Feedwater Transient and Stability benchmark with SIMULATE-3K
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

Y. Yun, C. Cozzo, O. Leray, H. Ferroukhi
Uncertainty and Sensitivity Study of Fuel Thermal Behaviour within OECD/NEA UAM Programme
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
NUSS-RF: Stochastic Sampling-Based Tool for Nuclear Data Sensitivity and Uncertainty Quantification
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

O. Leray, P. Grimm, M. Hursin, H. Ferroukhi and A. Pautz
Uncertainty Quantification of Spent Fuel Nuclide Compositions due to Cross-Sections, Decay Constants and Fission Yields
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

O. Leray, P. Grimm, H. Ferroukhi, and A. Pautz
Quantification of Code. Library and Cross-Section Uncertainty Effects on the Void Reactivity Coefficient of a BWR UO2 Assembly
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Effects of Advanced Radial Submeshing Methods on Pin Power Reconstruction for an EPR Core Design
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

M. Pecchia, A. Vasiliev, O. Leray, H. Ferroukhi, A. Pautz
New PSI Methodology for Manufacturing and Technological Uncertainty Quantification
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
Updated Validation of the PSI Criticality Safety Evaluation Methodology using MCNPX2.7 and ENDF/B-VII.1
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

D. Wicaksono, P. Grimm, A.Vasiliev, M. Hursin, G. Perret, and H. Ferroukhi
Validation of Two Monte Carlo Codes for LWR Burnup Calculations
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

P. Grimm, G. Perret, H. Ferroukhi
CASMO-4E and CASMO-5 Analysis of the Isotopic Compositions of the LWR-PROTEUS Phase II Burnt PWR UO2 Fuel Samples
Proc. Int. Conf. Reactor Physics, PHYSOR2014, Kyoto, Japan, September 28 - October 3, 2014

V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Analysis of Axial Fuel Relocation based on Gamma Scan data from OECD Halden Reactor Project LOCA Tests
Proc. Water Reactor Fuel Performance Meeting WRFPM2014, Sendai, Japan, September 14-17, 2014

V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Fuel Relocation in IFA-650 LOCA Tests Based on Gamma Scan Data
Proc. Enlarged Halden Project Group Meeting, Roeso, Norway, September 7-12, 2014

H. Perrier, O. Leray, M. Pecchia, A. Vasiliev, H. ferroukhi, A. Pautz
Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
American Nuclear Society 2014 Student Conference, PSU, Pennsylvania, USA, April 3-5, 2013

L. Rossinelli, M. Hursin. H. Ferroukhi, A. Pautz
Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
American Nuclear Society 2014 Student Conference, PSU, Pennsylvania, USA, April 3-5, 2013

A. Dupre, A. Vasiliev, H. Ferroukhi, A. Pautz
Validation Enhancements of the PSI Fast Neutron Fluence Computational Scheme using Operational PWR Experimental Data
American Nuclear Society 2014 Student Conference, PSU, Pennsylvania, USA, April 3-5, 2013

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2013

G. Khvotsov, A. Pautz, E. Kolstad, G. Ledergerber
Analysis of a Halden LOCA Test with the BWR High Burnup Fuel
Proc. LWR Fuel Performance Meeting - Top Fuel 2013, Charlotte, USA, September 15-19, 2013

R. Ngayam-Happy, M. Krack
Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide
Proc. European Material research Socitey Meeting E-MRS 2013, Strasbourg, France, May 27-31, 2013

J. Freixa, S. belaid, O. Zerkak
Thermal-Hydraulic System Code Performance for SBLOCA Phenomonelogy using Different geometries and Scales
Proc. Nuclear Reactor Thermal-Hydraulics NURETH-15, Pisa, Italy, May 12-17, 2013

K. Nikitin, T. Gudmunsson, S. Canepa, O. Zerkak, H. Ferroukhi, A. Pautz
Post-Analysis of a Turbine Trip Test at a BWR/6 using the TRACE/S3K Coupled Code
Proc. Nuclear Reactor Thermal-Hydraulics NURETH-15, Pisa, Italy, May 12-17, 2013

R. Szijarto, J. Freixa, H-M. Prasser
Implementation and Validation of a Condensation heat Transfer Model for Slightly Inclined Horizontal Pipes for RELAP5
Proc. Nuclear Reactor Thermal-Hydraulics NURETH-15, Pisa, Italy, May 12-17, 2013

C. Adamsson, D. Papini, O. Zerkak and H-M. Prasser
Simulation of International Standard Problem ISP-42 Phase B using In-House Coupled Code GOTHIC-TRACE
Proc. Nuclear Reactor Thermal-Hydraulics NURETH-15, Pisa, Italy, May 12-17, 2013

D. Papini, C. Adamsson, M. Andreani and H-M. Prasser
Simulation of International Standard Problem ISP-42 Phase B using the Containment Code GOTHIC
Proc. Nuclear Reactor Thermal-Hydraulics NURETH-15, Pisa, Italy, May 12-17, 2013

D. Caraghiaur, C. Adamsson, H. Anglart
Deposition of Inertial Drops in Eulerian Formulation
Proc. Nuclear Reactor Thermal-Hydraulics NURETH-15, Pisa, Italy, May 12-17, 2013

A. Dokhane, H. Ferroukhi, A. Pautz
On BWR Regional Oscillations with Rotational Symmetry Line using SIMULATE-3K
Proc. Mathematics and Computations M&C 2013, Sun Valley, USA, May 5-9, 2013

D. Wicaksono, O. Zerkak, K. Nikitin, H. Ferroukhi, A. Pautz
Application of Power Time-Projection on the Operator Splitting Coupling Scheme of the TRACE/S3K Coupled Code
Proc. Mathematics and Computations M&C 2013, Sun Valley, USA, May 5-9, 2013

M. Hursin, A. Vasiliev, H. Ferroukhi, A. Pautz
Comparision of SERPENT and CASMO-5M for Pressurized Water Reactors Models
Proc. Mathematics and Computations M&C 2013, Sun Valley, USA, May 5-9, 2013

S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Preparation of Nuclear Libraries with Deterministic and Stochastic Methods for LWR Reflectors
Proc. Mathematics and Computations M&C 2013, Sun Valley, USA, May 5-9, 2013

S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Convergence Studies of Deterministic Methods for LWR Explicit Reflector Methodology
Proc. Mathematics and Computations M&C 2013, Sun Valley, USA, May 5-9, 2013

S. Bogetic, M. Hursin, A. Dokhane, H. Ferroukhi, S. Canepa, A. Pautz
Comparison of U.S NRC PARCS against Studsvik SIMULATE-3 Core Simulator for Modeling and Analysis of Swiss PWRs
Proc. American Nuclear Society 2013 Student Conference, MIT, Boston, April 4-6, 2013

H. Ferroukhi, O. Leray, M. Hursin, A. Vasiliev, G. perret, A. Pautz
Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools
Proc. Nuclear Data Conference ND2013, New York City, USA, March 4-8, 2013

A. Vasiliev, H. Ferroukhi, T. Zhu, A. Pautz
Nuclear Data Library E ects on Fast to Thermal Flux Shapes around PWR Control Rod Tips
Proc. Nuclear Data Conference ND2013, New York City, USA, March 4-8, 2013

T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
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
Proc. Nuclear Data Conference ND2013, New York City, USA, March 4-8, 2013

T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, A. Pautz
Comparison of Two Approaches for Nuclear Data Uncertainty Propagation In MCNP(X) for Selected Fast Spectrum Critical Benchmarks
Proc. Nuclear Data Conference ND2013, New York City, USA, March 4-8, 2013

F. Ribeiro, G. Khvostov
Multi-scale approach to advanced fuel modelling for enhanced safety
Proc. EUROSAFE Meeting, Cologne, Germany, November 4-5, 2013 <

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2012

C. Adamsson, D. Papini, O.Zerkak, H-M. Prasser
Simulation of International Standard Problem ISP-42, Phases A and B with the TRACE Code
Proc. Int. Top. Mtg. Nuclear Thermal-Hydraulics, Operatio and Safety, NUTHOS-9, Kaohsiung, China, September 9-13, 2012

D. Papini, C. Adamsson, M. Andreani, H-M. Prasser
Study of Condensation Heat Transfer in Passive Safety Systems Using GOTHIC and TRACE Codes
Proc. Int. Top. Mtg. Nuclear Thermal-Hydraulics, Operatio and Safety, NUTHOS-9, Kaohsiung, China, September 9-13, 2012

C. Adamsson, D. Papini, O.Zerkak, H-M. Prasser
Simulation of Complex Transient Flow Patterns in the ESBWR Passive Containment Cooling System
Proc. Int. Top. Mtg. Nuclear Thermal-Hydraulics, Operatio and Safety, NUTHOS-9, Kaohsiung, China, September 9-13, 2012

R. Szijarto, J. Freixa, H-M. Prasser
Performance of Heat Transfer Models of Thermal-Hydraulic System Codes at the Invert Edwards Pipe Experiment
Proc. Int. Top. Mtg. Nuclear Thermal-Hydraulics, Operatio and Safety, NUTHOS-9, Kaohsiung, China, September 9-13, 2012

A. Vasiliev, W. Wieselquist, H. ferroukhi, S. Canepa, J. Heldt, G. Ledergerber
Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
Proc. Int. Conf. on Radiation Protection and Shielding, RPSD/ICRS-12, Nara, Japan, September 2-7, 2012

H. Ferroukhi, G. Khvostov, O. Zerkak, A. Vasiliev, M.A. Zimmermann
Evaluation of the Fuel Rod Behaviour in a BWR Spent Fuel Pool under Boil-Off Conditions
Proc. Int. Workshop on Nuclear Safety and Severe Accidents, NUSSA, Peking, China, September 7-8, 2012

M. Wagner, R. Kilger, A. Pautz, W. Zwermann, P.Grimm, A. Vasiliev, H. Ferroukhi
Validation of KENOREST with LWR-PROTEUS Phase II Samples
Proc. Jahrestagung Kerntechnik, May 22-24, 2012, Stuttgart, Germany, 2012

T. Zhu, A. Vasiliev, W. Wieselquist, H. Ferroukhi
Stochastic Sampling Method with MCNPX for Nuclear Data Uncertainty Propagation in Criticality Safety Applications
Proc. Int. Conf on Advances in Reactor physics, PHYSOR2012, Knoxville, Tennessee, USA, April 15-20, 2012

W. Wieselquist, A. Vasiliev, H. Ferroukhi
Nuclear Data Uncertainty Propagation in a Lattice Physics Code using Stochastic Sampling
Proc. Int. Conf on Advances in Reactor physics, PHYSOR2012, Knoxville, Tennessee, USA, April 15-20, 2012

P. Grimm, A. Vasiliev, W. Wieselquist, H. Ferroukhi, G. Ledergerber
Reactor Physics Studies for Assessment of Tramp Uranium Methods
Proc. Int. Conf on Advances in Reactor physics, PHYSOR2012, Knoxville, Tennessee, USA, April 15-20, 2012

H. Ferroukhi, A. Vasiliev, A. Dufresne, R. Chawla
Towards a Reference Numerical Scheme using MCNPX for PWR Control Rod Tip Fluence Estimations
Proc. Int. Conf on Advances in Reactor physics, PHYSOR2012, Knoxville, Tennessee, USA, April 15-20, 2012

A. Dokhane, S. Canepa, H. Ferroukhi
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss BWRs
Proc. Int. Conf on Advances in Reactor physics, PHYSOR2012, Knoxville, Tennessee, USA, April 15-20, 2012

D.R. Karanki, V.N. Dang, T-W. Kim
The Impact of Dynamics on the MLOCA Accident Model - An Application of Dynamic Event Trees
Proc. Int. Probabilistic Safety Assesment Conf.PSAM11/ESREL2012, Finland, June 25-29, 2012

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2011

K. Nikitin, A. Manera, H. Ferroukhi, J. Judd, G.M. Grandi
OECD/NEA Main Steam Line Break PWR Benchmark Simulation by TRACE/S3K Coupled Code
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

J. Freixa, T-W. Kim, A. Manera
Post-Test Thermal-Hydraulic Analysis of two Intermediate LOCA Tests at the ROSA Facility including Uncertainty Evaluation
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

J. Freixa, T-W. Kim, A. Manera
Testing of the QUICKTEST-ULTIMATE Algorithm to Solve the Dissolved Convection Equation during a Boron Dilution Test at the PKL Facility
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

V. Petrov, A. Manera
Validation of STAR-CCM+ for Bouyancy Driven Mixing in a PWR Reactor Pressure Vessel
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

A. Manera, H-M. Prasser, S. Leyer
Analysis of the Performance of the KERENA Emergency Condenser
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

T-W. Kim, A. Manera
Prediction of Void Fraction in a Subchannel and Bundle Geometry with FLICA4 and TRACE
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

O. Zerkak, I. Gajev, A. Manera, T. Kozlowski, A. Gommlich, S. Zimmer, S. Kliem, N. Crouzet, M.A. Zimmermann
Revisiting Temporal Accuracy in Neutronics/T-H Code Coupling using the NURESIM LWR Simulation Platform
Proc. Int. Top. Meetg. Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Canada, September 25-30, 2011

G. Khvostov, E. Kolstad, G. Ledergerber, M.A. Zimmermann, W. Wiesenack, O. Bremond, R. Restani, H. Wiese, M. Martin
Pre-calculation using the Falcon Fuel Behaviour code of the fuel rod design parameters and the test conditions for a two-run Halden LOCA tests with KKL BWR high-burnup fuel".
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011

G. Khvostov, W. Wiesenack, B.C. Oberlander, E. Kolstad, G. Ledergerber, M.A. Zimmermann
Post-Test Analysis of the Halden LOCA Experiment IFA-650.7 using the Falcon Code".
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011

E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Assessment of MCNPX/CINDER for Burnup Calculations
Proc. Int. Conf. on Nuclear Criticality ICNC 2011, Edinburgh, Scotland, September 19-22, 2011

E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Criticality Safety Evaluation of a Swiss Wet Storage Pool Including Limited BUC and Uncertainty Analysis
Proc. Int. Conf. on Nuclear Criticality ICNC 2011, Edinburgh, Scotland, September 19-22, 2011

G. Khvostov, M.A. Zimmerman, W. Lyon, M. Pytel
Towards Advanced Modelling of MPS-assisted Cladding Failure during Power Ramps using the FALCON Code
Proc. Water Reactor Fuel Performance Meeting 2011, Chengdu, China, September 11-14, 2011

A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa
Development and Test Validation of a Computational Scheme for High-Fidelity Fluence Estimations of the Swiss BWRs
Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nucl. Science and Engineering,(M&C2011), Rio de Janeiro, Brazil, May 8-12, 2011

W. Wieselquist, H. Ferroukhi, K. Bernatowicz
A Trend Analysis Methodology for Enhanced Validation of 3-D LWR Core Simulations
Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nucl. Science and Engineering,(M&C2011), Rio de Janeiro, Brazil, May 8-12, 2011

W. Wieselquist, A. Vasiliev, H. Ferroukhi
Towards an Uncertainty Quantification Methodology with CASMO-5
Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nucl. Science and Engineering,(M&C2011), Rio de Janeiro, Brazil, May 8-12, 2011

D. Bertolotto, A. Manera, R. Chawla
Development and Validation of a Coupled CFD/System-Code Tool
Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP2011), Nice, France, May 2-5, 2011

D.R. Karanki, V.N. Dang, T-W. Kim
Discted Dynamic Event Tree Analysis of MLOCA using ADS-TRACE ADS-TRACE
Proc. Top. Meetg. on Probabilistic Safety Assessment and Analysis, ANS PSA2011, Wilimington, US, March 13-17, 2011

J. Jimenez, M.A. Zimmermann, O. Zerkak, Ph. Emonot
Presentation of the Multi-Physics Subproject of the NURISP European Project
Proc. Annual Meeting of the Spanish Nuclear Society, Burgos, Spain, Sept. 28-30, 2011

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2010

T.W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Quantitative Analysis of Effect of Power Uprate on Core Damage Frequency of MBLOCA
Proc. Int. Mtg. on Nucl. Thermal-Hydraulics, Operation and Safety NUTHOS-8, Shanghai, China, October 10-14, 2010

J. Freixa, T-W. Kim, A. Manera
Thermal-Hydraulic Analysis of an Intermediate LOCA Test at the ROSA Facility including Uncertainty Evaluation
Proc. Int. Mtg. on Nucl. Thermal-Hydraulics, Operation and Safety NUTHOS-8, Shanghai, China, October 10-14, 2010

Y. Yun, G. Khvostov, J. Freixa, M.A. Zimmermann
Analysis of Fuel Rod Behaviour in EPR during base irradiation and LOCA-transient utilizing FALCON
Proc. LWR Fuel Performance TopFuel 2010 meeting, Orlando, Florida, USA, September 26-29, 2010

V. Petrov, A. Manera
Development and validation of a CFD model for the EPR pressure vessel
Proc. Int. Congress on Advances in Nuclear Power plants (ICAPP'10), San Diego, California, USA, June 13-17, 2010

D. Bertolloto,
Set-up of a Validation Strategy for the Coupled Code CFX/TRACE in the FLORIS Facility with the Aid of CFD Simulations
Proc. Int. Congress on Advances in Nuclear Power plants (ICAPP'10), San Diego, California, USA, June 13-17, 2010

H. Ferroukhi, K. Hofer
Coupled 3-D Neutronics/Thermal-Hydraulic Core Analysis of a BWR Nuclear Heating Transient
Proc. Int. Conf. Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR 2010 Pittsburgh, USA, May 9-14, 2010

K. Nikitin, J. Judd, G.M. Grandi, A. Manera, H. Ferroukhi
Peach Bottom 2 Turbine Trip 2 Simulation by TRACE/S3K Coupled Code
Proc. Int. Conf. Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR 2010 Pittsburgh, USA, May 9-14, 2010

A. Vasiliev, R. Pittarello, H. Ferroukhi, E. Kolbe
Verification of PWR In- and Ex- Vessel Neutron Fluence Calculations with MCNPX, based on the "H.B. Robinson-2" dosimetry Benchmark
Proc. Int. Conf. Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR 2010 Pittsburgh, USA, May 9-14, 2010

C. Aguirre, S. Opel, H. Ferroukhi, G. Grandi, L. Belblidia, M. Thunman, C. Rotander,B-G. Bergdahl, S. Baumgartner, G. Ledergerber
Benchmarking of Transient Codes against Cycle 19 Measurements at Leibstadt Nuclear Power Plant (KKL)
Proc. Int. Conf. Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR 2010 Pittsburgh, USA, May 9-14, 2010

T. Ivanova, F. Fernex, E. Kolbe, A. Vasiliev, G-S. lee, S-W. Woo, D. Mennerdahl, Y. Nagaya, J-C. Neuber, A. Hoefer, B. Rearden, D. Mueller, Y. Rugama OECD/NEA
Expert Group on Uncertainty Analysis for Criticality Safety Assessment: Current Activities
Proc. Int. Conf. Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR 2010 Pittsburgh, USA, May 9-14, 2010

W. Wieselquist
A Low-Order Quasidiffusion Discretization via Linear-Continuous Finite-Elements on Unstructure Triangular Meshes
Proc. Int. Conf. Advances in Reactor Physics to Power the Nuclear Renaissance, PHYSOR 2010 Pittsburgh, USA, May 9-14, 2010

E. Kolbe, A. Vasiliev, H. Ferroukhi
Assessment of the JEFF-3.1.1 Neutron data Library for CSE of LWR Fuel Storage Pools
Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2010, Jeju Island, Korea, 26-30 April, 2010

A. Vasiliev, R. Pittarello, E. Kolbe, H. Ferroukhi
Comparison of Neutron Data Libraries for the Analysis of the "H.B.Robinson-2 Pressure Vessel Benchmark" with the MCNPX Code
Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2010, Jeju Island, Korea, 26-30 April, 2010

G. Khvostov, M.A. Zimmermann, W. Wiesenack, G. Ledergerber
Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on HRP experiments and results of calculation by FALCON coupled with the FRELAX model
Proc. Enlarged HALDEN Group Meeting, Norway, 14-19 March 2010

F. Devynck, M. Krack
Core-Shell vs Rigid-Ion Model for the Study of Point Defects in UO2
Proc. Nuclear Materials 2010 Conference NuMath2010, Karlsruhe, Germany, October 4-7, 2010

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2009

J. Freixa, A. Manera
TRACE and RELAP5 Thermal-Hydraulic Analysis on Boron Dilution Tests at the PKL Facility
Proc. 13th Int. Topical. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-13, Kanazawa, Japan September 27-October 2, 2009

T-W. Kim, A. Manera, M.A. Zimmermann, V.N. Dang
Effect of Power Uprate on Exceedance Frequency during MBLOCA with Minimum Specifications for Success
Proc. 13th Int. Topical. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-13, Kanazawa, Japan September 27-October 2, 2009

A. Manera, H-M. Prasser, R. Lechner, T. Frank
Toward the prediction of Temperature Fluctuations by means of Steady RANS for the Estimation of Thermal Fatigue
Proc. 13th Int. Topical. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-13, Kanazawa, Japan September 27-October 2, 2009

K. Nikitin, A. Manera
Simulation of Reflood Experiments using the BEst-Estimate Thermal-Hydraulic Code TRACE
Proc. 13th Int. Topical. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-13, Kanazawa, Japan September 27-October 2, 2009

E. Kolbe, A. Vasiliev, H. Ferroukhi
Assessment of S(alpha,beta) Libraries for Criticality Safety Evaluations of Wet Storage Pools by Refined Trend Analyses
Proc. Nuclear Criticality Safety Division Topical Meeting NCSD 2009, Richland, Washington, US, September 13-17, 2009

G. Khvostov, M.A. Zimmermann, G. Ledergerber
Parametric Study of Fuel Rod Behaviour during the RIA using the Modified FALCON Code
Proc. OECD/NEA Workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents, Paris, France, September 9-11, 2009

G. Khvostov
A Dynamic Model for Fission Gas Release and Gaseous Swelling Integrated into the FALCON Fuel Analysis and Licensing Code
Proc. TOP Fuel 2009, Paris, France, September 6-10, 2009

M.A. Zimmermann, T-W. Kim, S. Laroche, A. Ui, S. Ebata, J-J. Jeong, H-G. Lim, S-H. Ahn, M. Gavrilas, J. Hortal
Towards quantification of plant safety margins - a status report
Proc. 13th Int. Topical. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-13, Kanazawa, Japan, September 27-October 2, 2009

A. Manera, H-M. Prasser, R. Lechner, T. Frank
Toward the prediction of Temperature Fluctuations by means of Steady RANS for the Estimation of Thermal Fatigue
Proc. 13th Int. Topical. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-13, Kanazawa, Japan, September 27-October 2, 2009

L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou
Insights into Fuel Rod Performance Codes during RAMPS: Results of a Code Benchmark based on the SCIP Project
Proceedings of TOP Fuel 2009, Paris, France, September 2009

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2008

D. Bertolotto , A. Manera, B.L. Smith, H-M. Prasser, R. Chawla
Single-phase mixing studies by means of a directly coupled CFD/system-code tool
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, September 14-19, 2008, Interlaken, Switzerland (CD-ROM,FP412)

D. Bertolotto , A. Manera, B.L. Smith, H-M. Prasser, R. Chawla
CFD Simulations of a Single-Phase Mixing Experiment
Proc.Int.Youth. Nuclear Congress IYNC 2008 September 20-26, 2008, Interlaken, Switzerland (CD-ROM,FP422)

H. H. FERROUKHI, J-M. Hollard, M.A. Zimmermann, R. Chawla
Estimation of the Fast Neutron Fluence at Control Rod Tips using a 3-D Diffusion/2-D Transport Calculation Scheme
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008

H. Ferroukhi , K. Hofer, J-M. Hollard, A. Vasiliev, M.A. Zimmermann
Core Modelling and Analysis of the Swiss Nuclear Power Plants for Qualified R&D Applications
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008

H. Ferroukhi , O. Zerkak, R. Chawla
Comparative Study of CORETRAN and SIMULATE-3K for Main Steam Line Break Analyses
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, September 14-19, 2008, Interlaken, Switzerland (CD-ROM,FP238)

A. Vasiliev, H. Ferroukhi, E. Kolbe, M.A. Zimmermann
On the use of importance factors from Monte Carlo calculations for efficient fast neutron fluence prediction
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008

P. Vinai, R. Macian-Juan, R. Chawla
Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008

O. Zerkak, H. Ferroukhi
Effects of the core inlet mixing modelling on a main steam line break analysis at hot full power
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008

G. Khvostov, M.A. Zimmermann, T. Sugiyama, T. Fuketa
On the use of the FALCON code for modeling the behaviour of high burn-up BWR fuel during the LS-1 pulse-irradiation test
Proc.Int.Conf.on the Physics of Reactors, PHYSOR'08, Interlaken, Switzerland, September 14-19, 2008

G. Khvostov, M.A. Zimmermann , G. Ledergerber, E. Kolstad, R. Montgomery
Parametric Study of the Behaviour of a Pre-Irradiated BWR Fuel Rod under Conditions of LOCA Simulated in the Halden In-Pile Test System with the FALCON Code
Proc.Water Reactor Fuel Performance Meetg.,WRFPM 2008, Seoul, Korea, 19-23 October, 2008

G. Khvostov, M.A. Zimmermann, R. Stoenescu, G. Ledergerber
Definition of optimal parameters of fuel rod design and test conditions for the high temperature LOCA experiment IFA-650.7 using the FALCON fuel behaviour code
Enlarged Halden Programme Group Meeting EHPGM 2008, Loen, Norway, 18-23 May, 2008

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2007

W. Barten, A. Manera, R. Macian-Juan
Assessment of the capability of the TRACE code to model propagation of linear acoustic pressure waves in one-dimensional flow
Proc. NURETH-12, Pittsburgh, USA, 30 September- 4 October, 2007

A. Manera, R. Macian-Juan
Assessment of TRACE film condensation models with and without non-condensable gases
Proc. NURETH-12, Pittsburgh, USA, 30 September- 4 Octo

A. Jasiulevicius, R. Macian-Juan
Assessment of the CHF Models in TRACE Code Against Rod Bundle Experimental Data
Proc. ICONE-15, Nagoya, Japan, April 22-26, 2007

A. Jasiulevicius, O. Zerkak, R. Macian-Juan
Simulation of ROSA-V Test 6.2 using TRACE v.4.274 code
Proc. ICONE-15, Nagoya, Japan, April 22-26, 2007

G. Khvostov, A. Romano, M.A. Zimmermann
Modeling the effects of axial fuel relocation in the IFA-650.4. LOCA test
Proc. Enlarged Halden Project Group Meeting, Storefjell, Norway, March 11-16, 2007

E. Kolbe, A. Vasiliev, M.A. Zimmermann
Validation of Standard Neutron Data Libraries for LWR Storage Pools and Transport Casks Criticality Safety Evaluation
Nuclear Data Conference, ND-2007, Nice, France, April 22-27, 2007

A. Vasiliev, H. Ferroukhi, M.A. Zimmermann .A.
On the Observation of Discrepancies in the O-16 (n,alpha) Data between Different Evaluated Nuclear Data Files,
Nuclear Data Conference, ND-2007, Nice, France, April 22-27, 2007

O. Zerkak, P. Coddington, N. Crouzet, E. Rover, J. Jimenez, D. Cuervo
LWR Multi-Physics Developments and Applications within the Framework of the NURESIM Europen Project
Proc. Int. Top. Meetg. on Mathematics &Computation and Supercomputing in Nuclear Applications, M&C+SNA 2007, Monterey, USA, April 15-19, 2007

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2006

Y. Aounallah, G. Khvostov, A. Romano, H. Wallin, M.A. Zimmermann, E. Kolstad, M. Ek, L. Kekkonen
Simulations of the Halden IFA-650.3/.4 High Burnup LOCA Test with TRACE and FALCON: a Preliminary Study on Axial Relocation
Proc. Int. Meetg. on LWR Fuel Performance TopFuel 2006, Salamanca, Spain, October 22-26, 2006,

W. Barten, A. Jasiulevicius, O. Zerkak, R. Macian-Juan
Analysis of UMSICHT Water Hammer Benchmark Tests: Results from PSI using TRACE and RELAP5 Codes
Proc. Int. Conf. on Hydroinformatics HIC 2006, Nice, France, September 4-8, 2006

A. Jasiulevicius, O. Zerkak, R. Macian-Juan
Investigation of Heat Transfer Mechanismus under Shutdown Plant Conditions with TRACEv4. 160
Proc. Int. Congress on Advances in Nuclear Power Plants ICAPP'06, Reno, USA, June 4-8, 2006

A. Jasiulevicius, R. Macian-Juan
Impact of Different Correlation on TRACEv4.160 Predicted Critical Heat Flux
Proc. Int. Congress on Advances in Nuclear Power Plants ICAPP'06, Reno, USA, June 4-8, 2006

Vinai P., R. Macian-Juan, Chawla R
A Methodology for the Quantification of Uncertainty in best Estimate Code Physical Models
Proc. Int. Congress on Advances in Nuclear Power Plants ICAPP'06, Reno, USA, June 4-8, 2006

A. Jasiulevicius, R. Macian-Juan
Predictions of Critical Heat Flux in Annular Pipes with TRACEv4.160 Code
Proc. Int. Conf. on Nuclear Engineering ICONE14, Miami, USA, July 17-20, 2006

A. Jasiulevicius, R. Macian-Juan
Steady-State Film Boiling Heat Transfer Simulated with TRACEv4.160
Proc. Int. Conf. on Nuclear Engineering ICONE14, Miami, USA, July 17-20, 2006

E. Kolbe, A. Vasiliev,M.A. Zimmermann
Assessment of Standard Point-wise Neutron Data Libraries for Criticality Safety Analysis with a Monte Carlo Code
Proc. PHYSOR-2006, 10-14, Vancouver, Canada, September 10-14, 2006

A. Vasiliev, H. FERROUKHI, M.A. Zimmermann
CASMO-4/SIMULATE-3/MCNPX Analysis of a Reactor Pressure Vessel Scraping Test
Proc. PHYSOR-2006, 10-14, Vancouver, Canada, September 10-14, 2006

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2005

W. Barten, A. Hermann, H. Wallin
Mechanical Modeling of Pressure Tube Tests Using the FEAT Code
Proc. Jahrestagung Kerntechnik 2005, Nuremberg, Germany, May 10-12, 2005

A. Dokhane, D. HENNIG, Rizwan-uddin, R. Chawla
Assessment of a BWR Analytical Reduced Order Model Against the System Code RAMONA: Applicability and Limitations
Proc. Int. Conf. on Nuclear Engineering ICONE13, Beijing, China, May 2005, 16-20, 2005

A. Dokhane, H. FERROUKHI, M.A. Zimmermann, C. Aguirre
A Reactor Noise Analysis Methodology for BWR Core Stability Evaluation: Application and Assessment to Leibstadt Stability Tests
Proc. Int. Top. Meetg. on Mathematics and Computation M&C 2005, Avignon, France, September 12-15, 2005

H. FERROUKHI, M.A. Zimmermann
Evaluation of the PWR REA Pulse Width for Realistic UO2/MOX Cores
Proc. Int. Top. Meetg. on Mathematics and Computation M&C 2005, Avignon, France, September 12-15, 2005

A. Vasiliev, J. Lebenhaft, M.A. Zimmermann
Analysis of MCNPX/JEF-2.2 and JENDL-3.3 Results for a Suite of the Low-enriched Thermal Compound Uranium Benchmarks
Proc. Int. Top. Meetg. on Mathematics and Computation M&C 2005, Avignon, France, September 12-15, 2005

A. Jasiulevicius, R. Macian-Juan, P. CODDINGTON, J. Sanchez
Assessment of TRACE Code against CHF Experiments
Proc. Int. Top. Meetg. on Nuclear Reactor Thermal Hydraulics NURETH-11, Avignon, France, October 2-6, 2005

A. Romano, M.A. Zimmermann
Effect of the Power Pulse Shape on the Fuel Thermal-Mechanical Response to RIAs: a Study Using FALCON and SCANAIR
Proc. Water Reactor Fuel Performance Meeting, WRFPM05, Kyoto, Japan, October 2-6, 2005

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2004

Aounallah Y.
Boilling Suppression in Convective Flow
Proc. ICAPP04, 13-17 June 2004, Pittsburgh, USA, CD-ROM, ISBN 0-89448-680-2)

W. Barten, P. CODDINGTON
RETRAN-3D Analysis of the Extreme Cases of Phase 3 of the Peach Bottom 2 Turbine Trip Benchmark
Jahrestagung Kerntechnik, 25-27 May 2004, Düsseldorf, Germany, Vol. Tagungsband, CD-ROM, 3-8, 2004 (ISSN 0720-9207, ISBN 3-9806415-6-2)

A. Dokhane, D. HENNIG, Rizwan-uddin, R. Chawla
Bifurcation Analysis using the System Code RAMONA
Proc. 12th International Conference on Nuclear Engineering (ICONE 12), 25-29 April 2004, Arlington, USA, CD-ROM, 2004 (ISBN 0-7918-3734-3)

R. Macian-Juan, M.A. Zimmermann, R. Chawla
Uncertainty Analysis Applied to Fuel Depletion Calculations
PHYSOR 2004, 25-29 April 2004, Chicago, USA, CD-ROM, 2004 (ISBN 0-89448-683-7)

R. Macian-Juan, M.A. Zimmermann,
Assessment of CASMO-4 Predictions of the Isotopic Inventory of High Burn-Up MOX Fuel
PHYSOR 2004, 25-29 April 2004, Chicago, USA, CD-ROM, 2004 (ISBN 0-89448-683-7)

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2003

Y. Aounallah, K. Hofer
Level-Swell Prediction with RETRAN-3D and its Application to a BWR Steam Line Break Analysis
International Congress on Advanced Nuclear Power Plants (ICAPP'03), 4-7 May 2003, Córdoba, Spain, CD-ROM

W. Barten, P. Coddington
Peach Bottom BWR Turbine Trip Benchmark Phase 3: Analysis of Full Plant System with 3D-Neutronics using RETRAN-3D
Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, USA, CD-ROM

J.R. Lebenhaft, H.R. Trellue
Validation of Monteburns for MOX Fuel using ARIANE Experimental Results
Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, USA, CD-ROM

A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using a Novel BWR Reduced Order Model: Part 1 - The Effects of Using Drift Flux Versus homogeneous Equilibrium Models
ICONE11, 20-23 April 2003, Tokyo, Japan, CD-ROM

A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using a Novel BWR Reduced Order Model: Part 2 - Stability Limits of In-phase and Out-of-phase Modes
ICONE11, 20-23 April 2003, Tokyo, Japan, CD-ROM

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2002

W. Barten, P. CODDINGTON, H. FERROUKHI
Peach Bottom BWR Turbine Trip Benchmark: PSI Analysis of Exercise 1 using RETRAN-3D
Physor 2002, 7-10 October 2002, Seoul, Korea, CD-ROM

A. Dokhane, D. HENNIG, RIZWAN-UDDIN, R. Chawla
Stability and Bifurcation Analyses of Two-Phase Flow Using a Drift Flux Model and Bifurcation code BIFDD
Tenth International Conference on Nuclear Engineering (ICONE-10), 14-18 April 2002, Arlington, Virginia, USA, CD-ROM

A. Dokhane, D. HENNIG, RIZWAN-UDDIN, R. Chawla
A Parametric Study of Heated Channels with Two-Phase Flow Using Bifurcation Analysis
American Nuclear Society Annual Meeting, June 9-13, 2002, Florida, USA, Trans. ANS, Vol. 86, 131-133 (2002)

A. Dokhane, D. HENNIG, RIZWAN-UDDIN, R. Chawla
Nonlinear Stability Analysis with a Novel BWR Reduced Order Model
Physor 2002, 7-10 October 2002, Seoul, Korea, CD-ROM

H. FERROUKHI, W. Barten, P. CODDINGTON
Transient 3-D Neutron Kinetic Analysis with CORETRAN of a Core Thermal-Hydraulic Boundary Condition Model - Peach Bottom 2 Turbine Trip Benchmark Phase 2
Physor 2002, 7-10 October 2002, Seoul, Korea, CD-ROM

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2001

H. FERROUKHI, P. CODDINGTON
Analysis and Sensitivity Studies with CORETRAN and RETRAN-3D of the NEACRP Rod Ejection Benchmark
ICONE-9, Nice France, April 8-12, 2001.

W. Barten, P. CODDINGTON, SULLIVAN J.
Development of a Model for RETRAN-3D for Pressure Losses at T-Junctions
ICONE-9, Nice France, April 8-12, 2001.

ANALYTIS G. TH, P. CODDINGTON
Analysis of Different Hypothetical Recirculation Line SB-LOCAs in KKM by TRAC-BF1/v98.1
ICONE-9, Nice France, April 8-12, 2001.

R. MACIAN, L. NECHVATAL
Best Estimate Analysis of the Thermal Expansion Scenario during Shutdown in a PWR
ICONE-9, Nice France, April 8-12, 2001.

AOUNALLAH Y.
CORETRAN/VIPRE Assembly Critical Power Assessment Against NUPEC BWR Experiments
ICONE-9, Nice, France, April 8-12, 2001.

W. Barten
RETRAN-3D Results and One-Dimensional Analytical Model for the Critical Power of a Rod Bundle with Cosine-shape Heating
Jahrestagung Kerntechnik 2001, Dresden, Germany, May 15-17, 2001.

H. FERROUKHI, P. CODDINGTON
Uncontrolled Rod Bank Withdrawal Benchmark Analysis with CORETRAN and RETRAN-3D
Submitted to the 2001 ANS International Meeting on Mathematical Methods for Nuclear Applications, MC-2001, Salt Lake City, September 2001.

J-M. Parratte, P. Grimm
Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Proc. ANS Topical Meeting On Practical Implementation of Nuclear Criticality Safety, NCSD, Reno, Nevada, USA, November 11-15, 2001

ASKARI B., BEHRINGER K., D. HENNIG
Some Remarks to Time Series Analysis for BWR Stability Analysis
Submitted to the 2001 ANS International Meeting on Mathematical Methods for Nuclear Applications, MC-2001, Salt Lake City, September 2001.

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2000

R. Macian, P. Coddington
Assessment of RETRAN-3D against experimental Loss of Coolant Scenarios
Proceedings of ICONE-8, Baltimore, MD, USA 2000.

R. Macian, Y. Aounallah, P. P. CODDINGTON Stangroom
Assessment of RETRAN-3D and VIPRE-02 Void Predictions against Experimental Data
Proceedings of ICONE-8, Baltimore, MD, USA 2000.

H. Ferroukhi, P. Coddington, F. Holzgrewe
Towards a Best-Estimate Approach to a Steady-State and Transient Analysis using the CORETRAN Code
International Meeting on Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, DC, USA, Nov. 2000

G. Th Analytis, P. Coddington
Development and Assessment of TRAC-BF1 for BWR LOCA Applications
International Meeting on Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, DC, USA, Nov. 2000

F. Holzgrewe, et al.
Validation of CASMO-4 Against SIMS Measured Spatial Nuclide Distributions Inside a 9 wt% Gd BWR Pin
Int. Topical Meeting on Light Water Reactor Fuel Performance, Park City, UT, USA, April 2000.

M. A. Zimmermann, W. van Doesburg
Current and Future Applications of thermal-Hydraulic and Neutronic Best-Estimate Methods in Support of the Swiss Licensing Process
CSNI/OECD Workshop on Advanced Thermal-Hydraulic and Neutronic Codes: Current and Future Applications, Barcelona, Spain, April 10-13, 2000.

P. Coddington, R. Macian
A Study of the Performance of Void Fraction Correlations used in the Context of Drift-Flux Two-Phase Flow Models
Presented at the International Meeting on Trends in Numerical and Physical Modelling for Industrial Multiphase Flows , Cargese, Corsica, September 27-29, 2000.

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1999

D. Ginestar, D. Hennig, R. Miro, G. Verdu
Remarks on Regional Power Oscillations in BWR's
Int. Conference on Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Spain, Sept 27-30, 1999

R. Macian, P. Cebull, P. Coddington, M. Paulsen
Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN- 3D
9th Int. Meeting on Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, CA

Y. Aounallah, P. Coddington
VIPRE-02 Subchannel validation against NUPEC void fraction data
9th Int. Meeeting on Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, CA

P. Coddington, Y. Aounallah, D. Maier, D. Reedha
Analysis of Rod Bundle and Subchannel, Subcooled Boiling Experiments using RETRAN-3D, TRAC-BF1 and VIPRE-02
9th Int. Meeting on Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, CA

G. Th. Analytis, D. Hennig, J. K-H. Karlsson
The Physical Mechanism of Core-Wide and Local Instabilities at the Forsmark-1 BWR
9th Int. Meeting on Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, CA

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1998

D. Maier, P. Coddington
Assessment of the Slip Options in RETRAN-3D Against a Wide Range of Rod Bundle Void Data
Paper ICONE6-6161, 6th International Conference on Nuclear Engineering, May 10-15, 1998, San Diego, California, USA

D. Hennig
Einige Bemerkungen zum physikalischen Mechanismus der Entstehung von oszillatorischen Instabilitäten in Siedewasserreaktoren
Jahrestagung Kerntechnik Mai 1998, München.

D. Maier, P. Coddington
Evaluation of the Slip Options in RETRAN-3D
9th International RETRAN Meeting, June 7-10, 1998, Monterey, CA, USA

Y. Aounallah, P. Coddington
VIPRE-02 Subchannel Validation Against NUPEC BWR Void Fraction Data
9th International RETRAN Meeting, June 7-10, 1998, Monterey, CA, USA

R. Macian, P. Cebull, P. Coddington, M. Paulsen
Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN-3D
9th International RETRAN Meeting, June 7-10, 1998, Monterey, CA, USA

D. Hennig
BWR Stability Analysis at PSI
Int. Conference on the Physics of Nuclear Science and Technology, Oct. 5 - 8, 1998, Long Island, New York

Top

1997

B. Brodbeck, P. Coddington
Evaluation of the TRAC-BF1 Code Against BWR/6 Start-up Tests
ICONE5, Nice France, May 26-30, 1997, paper no. 2461.

D. Maier, P. Coddington
Review of Wide Range Void Correlations Against an Extensive Database of Rod Bundle Void Measurements
ICONE5, Nice, France, May 26-30, 1997, paper no. 2434.