STARS Publications - Scientific Journals

2017

J. Li, D. Rochman, J. Herrero, A. Vasiliev, H. Ferroukhi, A. Pautz, M. Seidl, D. Janin
UO2 fuel pin bowing effects on isotopic concentrations
Annals of Nuclear Energy, Vol. 105 pp. 361-368 (2017)
http://dx.doi.org/10.1016/j.anucene.2017.03.038

M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses
Annals of Nuclear Energy, Vol. 105 pp. 121-132 (2017)
http://dx.doi.org/10.1016/j.anucene.2017.03.008

A. Dokhane, J. Judd, I. Gajev, O. Zerkak, H. Ferroukhi, T. Kozlowski
Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
Annals of Nuclear Energy, Vol. 102 pp. 190-199 (2017)
http://dx.doi.org/10.1016/j.anucene.2016.12.015

P. Helgesson, H. Sjoestrand, A.J. Koning, J. Ryden, D. Rochman, E. Alhassan, S. Pomp
Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances
Progress in Nuclear Energy, Vol. 96, pp. 76-96 (2017)
http://dx.doi.org/10.1016/j.pnucene.2016.11.006

D. Bocharov, M. Chollet, M. Krack, J. Bertsch, D. Grolimund, M. Martin, A. Kuzmin, J. Purans, E. Kotomin
Analysis of the U L3-edge X-ray absorption spectra in UO2 using molecular dynamics simulations
Progress in Nuclear Energy, Vol. 94, pp. 187-193 (2017)
http://dx.doi.org/10.1016/j.pnucene.2016.07.017

A. Aures, F. Bostelmann, M. Hursin, O. Leray
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
Annals of Nuclear Energy, Vol. 101 pp. 262-269 (2017)
http://dx.doi.org/10.1016/j.anucene.2016.11.001

M. Hursin, S. Bogetic, A. Dohkane, S. Canepa, O. Zerkak, H. Ferroukhi, A. Pautz
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
Annals of Nuclear Energy, Vol. 101 pp. 559-575 (2017)
http://dx.doi.org/10.1016/j.anucene.2016.11.001

D.Rochman, S.Goriely, A.J.Koning, H.Ferroukhi
Radiative neutron capture: Hauser Feshbach vs.statistical resonances
Physics Letters B, Vol. 764, pp. 109–113 (2017)
http://dx.doi.org/10.1016/j.physletb.2016.11.018

D. Rochman, O. Leray, M. Hursin, H. Ferroukhi, A. Vasiliev, et. al.
Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
Nuclear Data Sheets, Vol. 139 pp. 1-76 (2017)
http://dx.doi.org/10.1016/j.nds.2017.01.001

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2016

G. Khvostov, W. Wiesenack
Analysis of selected Halden overpressure tests using the FALCON code
Nuclear Engineering and Design, Vol. 310, pp. 395-409,(2016)
http://dx.doi.org/10.1016/j.nucengdes.2016.10.033

A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Towards a Consolidated Approach for the Assessment of Evaluation Models of Nuclear Power Reactors
Nuclear Technology, Vol.196, pp. 223-237, (2016)
http://dx.doi.org/10.13182/NT16-47

M. Pecchia, D. Wicaksono, P. Grimm, A. Vasiliev, G. Perret, H. Ferroukhi, A. Pautz
Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
Annals of Nuclear Energy, Vol. 97, pp. 153-164, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.07.001

A. Dokhane, H. Ferroukhi, A. Pautz
Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
Annals of Nuclear Energy, Vol. 96, pp. 344-353, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.06.016

T. Zhu, A. Vasiliev, H. Ferroukhi, D. Rochman, A. Pautz
Testing the Sampling-Based NUSS-RF Tool for the Nuclear Data–Related Global Sensitivity Analysis with Monte Carlo Neutronics Calculations
Nuclear Science and Engineering, Vol. 184, (2016)
http://dx.doi.org/10.13182/NSE14-142

V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
Nuclear Engineering and Design, Vol. 305, pp. 559-568 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2016.06.021

E. Alhassan, H. Sjöstrand, P. Helgesson, M. Österlund, S. Pomp, A.J. Koning, D. Rochman
Selecting benchmarks for reactor simulations: An application to a lead fast reactor
Ann. Nucl. Energy 2016, Vol. 96, pp. 158-169 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.05.033

D. Rochman, O. Leray, A. Vasiliev, H. Ferroukhi, A.J. Koning, M. Fleming, J.C. Sublet
A Bayesian Monte Carlo method for fission yield covariance information
Ann. Nucl. Energy 2016, Vol. 95, pp. 125-134, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.05.005

D. Rochman, O. Leray, G. Perret, A. Vasiliev, H. Ferroukhi, A.J. Koning
Re-evaluation of the thermal neutron capture cross section of 147Nd
Ann. Nucl. Energy 2016, Vol. 94, pp. 612-617, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.03.024

O. Leray, D. Rochman, P. Grimm, H. Ferroukhi, A. Vasiliev, M. Hursin, G. Perret, A. Pautz
Nuclear data uncertainty propagation on spent fuel nuclide compositions
Ann. Nucl. Energy 2016, Vol. 94, pp. 603-611, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.03.023

P. Helgesson, H. Sjöstrand, A.J. Koning, J. Rydén, D. Rochman, E. Alhassan, S. Pomp
Sampling of systematic errors to estimate likelihood weights in nuclear data uncertainty propagation
Nuclear Instruments and Methods in Physics Research A807, pp. 137–149, (2016)
http://dx.doi.org/10.1016/j.nima.2015.10.024

V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, W. Wiesenack
Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data
Nuclear Engineering and Design, Vol. 300, pp. 97–106 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.11.023

R. Puragliesi, L. Zhou, O. Zerkak, A. Pautz
Steady-state CFD simulations of an EPRTM reactor pressure vessel: A validation study based on the JULIETTE experiments
Nuclear Engineering and Design, Vol. 300, pp. 41–56 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.12.025

A. Vasiliev, H. Ferroukhi, M. Pecchia, A. Pautz
Localized neutron flux assessment and verification studies using MCNPX PWR full core model
Ann. Nucl. Energy, Vol. 92, pp. 317-332 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.01.026

P. Froidevaux, Pascal, F. Bochud, S. Baechler, V. Castella, M. Augsburger, C. Bailat, K. Michaud, M. Straub, M. Pecchia, T-M. Jenk, T. Uldin, P. Mangin
Po-210 poisoning as possible cause of death: forensic investigations and toxicological analysis of the remains of Yasser Arafat
Forensic Science International, Vol. 259, pp. 1-9 (2016)
http://dx.doi.org/10.1016/j.forsciint.2015.09.019

D. Rochman, A. Vasiliev, H. Ferroukhi, T. Zhu, S.C. van der Marck, A.J. Koning
Nuclear data uncertainty for criticality safety: Monte Carlo vs. linear perturbation
Ann. Nucl. Energy, Vol. 92, pp. 150-160 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.01.042

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2015

D. Rochman, A.J. Koning, S.C. van der Marck
Improving neutronics simulations and uncertainties via a selection of nuclear data
European Physical Journal A, Vol. 51 (2015)

E. Alhassan, H. Sjoestrand, P. Helgesson, M. Oesterlund, S. Pomp, A.J. Koning, D. Rochman
On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
Progress in Nuclear Energy Vol.88, pp. 43-52 (2016)

M. Pecchia, C.Parisi, F. D’Auria, O. Mazzantini%
Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR
Annals of Nuclear Energy, Vol. 85, pp. 271–278 (2015)

R. Ngayam-Happy, M. Krack, A. Pautz
Effects of stoichiometry on the defect clustering in uranium dioxide
Journal of Physics: Condensed Matter, Vol. 27, 455401,(2015)

C. Fiorina, I. Clifford, M. Aufiero, K. Mikityuk
GeN-Foam: a novel OpenFOAM based multi-physics solver for2D/3D transient analysis of nuclear reactors
Nuclear Engineering and Design, Vol. 294, pp. 24-37, (2015)

J.J. Herrero, A.Vasiliev, M. Pecchia, H.Ferroukhi, S. Caruso
Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
Annals of Nuclear Energy, Vol. 87, pp. 48-57,(2016)

A. Dupré, A. Vasiliev, H. Ferroukhi, A. Pautz
Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
Annals of Nuclear Energy, Vol. 85, pp. 820–829, (2015)

F. Ribeiro, G.Khvostov
Multi-scale approach to advanced fuel modelling for enhanced safety
Progress in Nuclear Energy, Vol. 84, pp. 24-35, (2015)

M. Krack
On the ground state electronic structure of uranium dioxide
Physica Scripta, Vol. 90, 094014 (2015)

M. Bertolus, M. Freyss, B. Dorado, G. Martin, K. Hoang, S. Maillard, R.Skorek, P. Garcia, C. Valot, A. Chartier, L. Van Brutzel, P. Fossati, R. W. Grimes, D. C. Parfitt, C. L. Bishop, S. T. Murphy, M. J.D. Rushton, D. Staicu, E. Yakub, S. Nichenko, M. Krack, F. Devynck, R. Ngayam-Happy, K. Govers, C.S. Deo, R. K. Behera
Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation
Journal of Nucl. Materials Vol. 462, pp. 475-495 (2015)

G. Jimenez, J.J. Herrero, A. Gommlich, S. Kliem, D. Cuervo, J. Jimenez
Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project
Ann. Nuclear Energy Vol. 84, pp. 86-97 (2015)

O. Zerkak, T. Kozlowski, I. Gajev
Review of multi-physics temporal coupling methods for analysis of nuclear reactors
Ann. Nuclear Energy Vol. 84, pp. 225-233 (2015)

T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz, S. Tarantola
NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification
Journal of Nuclear Science and Technology, Vol. 52, pp. 1000-1007, (2015)

M. Pecchia, A.Vasiliev, O.Leray, H.Ferroukhi, A.Pautz
Criticality Safety Evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
Ann. Nucl. Energy, Vol. (83), pp. 226-235 (2015)

M. Pecchia, A.Vasiliev, O.Leray, H.Ferroukhi, A.Pautz
Advanced calculation methodology for manufacturing and technological parameters uncertainties propagation at arbitrary level of lattice elements grouping
Journal of Nuclear Science and Technology, Vol. 52, pp. 1084-1092, (2015)

J. Freixa V. Martínez-Quiroga, O. Zerkak, F. Reventós
Modelling guidelines for core exit temperature simulations with system codes
Nucl. Eng. Design, Vol. 286, pp. 116-129 (2015)

T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method
Ann. Nucl. Energy, Vol. 75, pp. 713-722 (2015)

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2014

M. Demeshko, A. Dokhane, T. Washio, H. Ferroukhi, Y. Kawahara, C. Aguirre
Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event
Ann. Nucl. Energy, Vol. 75, pp. 645-657 (2014)

D. Papini, C. Adamsson, M. Andreani, H-M. Prasser
Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
Nucl. Eng. Design, Vol. 278, pp. 542-557 (2014)

A. Vasiliev, H. Ferroukhi, T. Zhu, A. Pautz
Nuclear Data Library Effects on Fast to Thermal Flux Shapes Around PWR Control Rod Tips
Nuclear Data Sheets, Vol. 118, pp. 575-578 (2014)

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
Nuclear Data Sheets, Vol. 118, pp. 498-501 (2014)

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
Nuclear Data Sheets, Vol. 118, pp. 453-455 (2014)

T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, A. Pautz
Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks
Nuclear Data Sheets, Vol. 118, pp. 388-391 (2014)

G. Martin, P. Garcia, C. Sabathier, F. Devynck, M. Krack, S. Maillard
A thermal modelling of displacement cascades in uranium dioxide
Nuclear Instruments and Methods in Physics Research B , Vol. 327, pp 108-122 (2014)

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
Progress in Nuclear Science and Technology, Vol. 4, pp. 99-103 (2014)

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2013

A. Dokhane, H. Ferroukhi, A. Pautz
On out-of-phase higher mode oscillations with rotation and oscillation of symmetry line using an advanced integral stability methodology
Annals of Nuclear Energy, Vol. 67, pp. 21-30 (2014)

R. Ngayam-Happy*, M. Krack
Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide
Progress in Nuclear Energy, Vol. 72, pp. 38-43 (2014)

A. Dokhane, S. Canepa, H. Ferroukhi
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss Boiling Water Reactors
Nuclear Technology, Vol. 183, pp. 341-353 (2013)

G. Khvostov, W. Lyon, M.A. Zimmermann
Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface
Annals of Nuclear Energy 62 (2013), pp. 398-412 (2013)

J. Freixa, W-W. Kim, A. Manera
Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design, Vol. 264, pp 153-160 (2013)

J. Rabone, M. Krack
A procedure for bypassing metastable states in local basis set DFT+U calculations and its application to uranium dioxide surfaces
Computational Materials Science, Vol. 71, pp 157-164 (2013)

W. Wieselquist, T. Zhu, A. Vasiliev, H. Ferroukhi
PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I
Science and Technology of Nuclear Installations, Volume 2013, Article ID 549793 (2013)

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2012

Y. Aounallah
Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
Kerntechnik, Vol 77, pp 316-323 (2012)

M. Sharabi, J. Freixa
Analysis of the ISP-50 Direct vessel Injection SBLOCA in the ATLAS Facility witth the RELAP5/MOD3.3 Code
Nuclear Engineering and Technology, Vol. 44, pp 709-718 (2012)

T-W. Kim, V. Petrov, A. Manera, S. Lo
Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes
Science and Technology of Nuclear Installations, Vol.2012, Article ID 746467 (2012)

T-W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Quantitative evaluation of change in core damage frequency by postulated power uprate: Medium-break loss-of-coolant-accidents
Annals of Nuclear Energy, Vol. 47, September 2012, pp. 69-80 (2012)

F. Devynck, M. Iannuzzi, M. Krack
Frenkel pair recombinations in UO2: Importance of explicit description of polarizability in core-shell molecular dynamics simulations
Physical Review B 85, 184103 (2012)

J. Freixa, A. Manera
Remarks on Consistent Development of Plant Nodalizations: An Example of Application to the ROSA Integral Test Facility
Science and Technology of Nuclear Installations, Vol. 2012, Article ID 158617 (2012)

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2011

V. Petrov, A. Manera
Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR - CFD investigations and comparison with experimental results
Nuclear Engineering and Design, Vol. 241, Issue 5, May 2011, pp 1476-1485 (2011)

E. Kolbe, A. Vasiliev, H. Ferroukhi
Assessment of the JEFF-3.1.1 Neutron Data Library for CSE of LWR Fuel Storage Pools
Journal of the Korean Nuclear Society, Vol. 59, pp. 1174-1178 (2011)

K. Nikitin, A. Manera
Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code
Nuclear Engineering and Design, doi: 10.1016/j.nucengdes2011.03.021 (2011)

G. Khvostov
A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code
Nuclear Engineering and Design, Vol. 241, pp 2983-3007 (2011)

G. Khvostov, W. Wiesenack, M.A. Zimmermann, G. Ledergerber
Some insights into the role of axial gas flow in fuel rod behaviour durinf the LOCA based on HALDEN tests and calculations with the FALCON-PSI code
Nuclear Engineering and Design, Vol. 241, Issue 5, May 2011, pp 1500-1507 (2011)

J. Freixa, A. Manera
Verification of a TRACE EPR model on the basis of a scaling calculation of an SBLOCA ROSA test
Nuclear Engineering and Design, Volume 241, Issue 3, March 2011, p 888-896 (2011)

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2010

D. Bertolotto, A. Manera, R. Macian-Juan, R. Chawla
Improvements of the one-dimensional dissolved solute convection equation using the QUICKEST-ULTIMATE algorithm
Nucl. Eng. Design, doi:10.1016/j.nucengdes.2010.10.021 (2010)

O. Zerkak, H. Ferroukhi
Vessel coolant mixing effects on a PWR Main Steam Line Break transient
Annals of Nuclear Energy, doi:10.1016/j.anucene.2010.08.016 (2010)

A. Vasiliev, H. Ferroukhi, E. Kolbe
Performance of a Monte-Carlo Solution to the H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
Annals of Nuclear Energy 37(2010), pp. 1404-1410, 2010

Y. Aounallah
Development of a Wide-Range Pre-CHF Convective Boiling Correlation
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 47(4), pp. 357-366, 2010

J. Freixa, A. Manera
Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE
Nuclear Engineering and Design, Available online 30 March, 2010

E. Kolbe, A. Vasiliev, H. Ferroukhi
The Effect of Modern Thermal Neutron Scattering Sublibraries on Criticality Safety Evaluations of Wet Storage Pools
Annals of Nuclear Energy, Vol. 37, pp. 371-379, 2010

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2009

H. Ferroukhi, O. Zerkak, R. Chawla
Cross-Section Modelling Effects on Pressurised Water Reactor Main Steam Line Break Analyses
Annals of Nuclear Energy, Volume 36, Issue 8, pp. 1184-1200, August 2009

H. Ferroukhi, M.A. Zimmermann
Study of the PWR REA Pulse Width for Realistic UO2 and MOX Core Designs using 3-D Kinetics
Annals of Nuclear Energy, Volume 36, Issue 8, pp. 1170-1183, August 2009

D. Bertolloto, A. Manera, S. Frey, H-M. Prasser, R. Chawla
Single-Phase Mixing Studies by means of a Directly Coupled CFD/System-code Tool
Annals of Nuclear Energy, Volume 36, Issue 3, pp 310-316 , April 2009

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 Multi-Step Calculation Scheme
Annals of Nuclear Energy, Volume 36, Issue 3, pp 286-291 , April 2009

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2008

Y. Aounallah
A Separate-Effect-Based New Appraisal of Convective Boiling and its Suppression
Journal of Nucl. Sci. and Techn. (ISSN 0022-3131), 45(2), 149-159 (2008)

W. Barten, A. Manera A., R. Macian-Juan
One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE
Nucl. Eng. Des. (ISSN 0029-5493), 238, 2568-2582 (2008)

W. Barten, A. Jasiulevicius, A. Manera, R. Macian-Juan, O. Zerkak
Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5
Nucl. Eng. Des. (ISSN 0029-5493), 238, 1129-1145 (2008)

E. Kolbe, A. Vasiliev, H. Ferroukhi, M.A. Zimmermann
Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems
Ann. Nucl. Energy (ISSN 0306-4549), 35, 1831-1841 (2008)

A. Vasiliev, E. Kolbe, M.A. Zimmermann
Towards the Development of Upper Subcriticality Limits on the Basis of Benchmark Criticality Calculations
Ann. Nucl. Energy (ISSN 0306-4549), 35, 1831-1841 (2008)

A. Vasiliev, H. Ferroukhi, M.A. Zimmermann, R. Chawla
On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test
Ann. Nucl. Energy (ISSN 0306-4549), 35, 565-569 (2008)

A. Vasiliev, E. Kolbe, H. Ferroukhi, M.A. Zimmermann, R. Chawla
On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
Ann. Nucl. Energy (ISSN 0306-4549), 35, 2432-2435 (2008)

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2007

A. Dokhane, D. Hennig, Rizwan-uddin, R. Chawla
BWR Stability and bifurcatio analysis using reduced order models and system codes: Identification of a subcritical Hop Bifurcation using RAMONA
Annals of Nuclear Energy, Volume 34, Issue 10, October 2007, pp 792-802 (2007)

A. Dokhane, D. Hennig, Rizwan-uddin, R. Chawla
Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis
Annals of Nuclear Energy, Volume 34, Issue 4, April 2007, pp 271-287 (2007)

R. Macian-Juan, M.A. Zimmermann M.A., R. Chawla
Statistical Uncertainty Analysis Applied to Fuel Depletion Calculations
J. of Nuclear Science and Technology, 44, 875-885 (2007)

H. Ferroukhi, J-M. Hollard, O. Zerkak, P. Coddington
PWR Cell Calculations using APOLLO-2 within the NURESIM Benchmark Framework
Trans. Am. Nuc. Soc., Vol. 97, pp. 703-704 (2007)

O. Zerkak, P. Coddington
Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
Nuclear Science and Engineering, 237(11), 1195-1208 (2007)

A. Vasiliev, H. Ferroukhi, M.A. Zimmermann, R. Chawla
Development of a CASMO-4/SIMULATE-3/MCNPX Calculation Scheme for PWR Fast Neutron Fluence Analysis and Validation against RPV Scraping Test Data
Annals of Nuclear Energy, 34(8), pp 615-627 (2007)

P. Vinai, R. Macian-Juan, R. Chawla
A statistical methodology for quantification of uncertainty in best estimate code physical models
Annals of Nuclear Energy, 34 (8), 628-640 (2007)

O. Zerkak, P. Coddington
Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
Nuclear Science and Engineering, 237(11), 1195-1208 (2007)

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2006

W. Barten, P. Coddington, H. Ferroukhi
RETRAN-3D Analysis of the BAse Case and the Four Extreme Cases of the OECD/NEA Peach Bottom 2 Turbine Trip Benchmark
Annals of Nuclear Energy 33, pp 99-118 (2006)

A. Dokhane, H. Ferroukhi, M.A. Zimmermann, C. Aguirre
Spatial and model-order based reactor signal analysis methodolgy for BWR core stability evaluation
Annals of Nuclear Energy, Volume 33, Issue 16, November 2006, pp 1329-1338 (2006)

A. Romano, H. Wallin, M.A. Zimmermann, R. Chawla
Modeling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
Nucl. Eng. Des. (ISSN 0029-5493), 236, 284-294 (2006)

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2005

A. Dokhane, D. Hennig, R. Chawla, Rizwan-uddin
Semi-Analytical Bifurcation Analysis of Two-Phase Flow in a Heated Channel
Int. J. Bifurcation Chaos (ISSN 0218-1274), 15, 2395-2409 (2005)

A. Jasiulevicius, Zerkak O., R. Macian-Juan
Loss of Residual Heat Removal System: Simulation by TRACEv4.00 Simulation of a PKL Experiment Trans. Am. Nuc. Soc., Vol. 92, pp. 442-443, June 2005

A. Jasiulevicius, R. Macian-Juan
CHF Experiments in Single Tubes TRACEv4.050 Code Validation Trans. Am. Nuc. Soc., Vol. 92, pp. 430-432, June 2005

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2004

Aounallah Y.
Void Fraction and Critical Power Assessment of CORETRAN-01/VIPRE-02
Nucl. Technol. (ISSN 0029-5450), 145, 163-176 (2004)

Barten W., Ferroukhi H., Coddington P.
Peach Bottom BWR Turbine Trip Benchmark Analyses with RETRAN-3D and CORETRAN
Nucl. Sci. Eng. (ISSN 0029-5639), 146, 306-324 (2004)

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2003

FERROUKHI H., CODDINGTON P.
The Analysis of PWR and BWR Reactivity Transients with CORETRAN and RETRAN-3D
Nuclear Technology, 142, 19-34 (2003)

KASEMEYER U., HELLWIG CH., LEBENHAFT J., CHAWLA R.
Comparison of Various Partial Light Water Reactor Core Loadings with Inert Matrix and Mixed-Oxide Fuel
Journal of Nuclear Materials, 319, 142-153 (2003)

MACIAN R., CODDINGTON P., STANGROOM P.
Assessment of RETRAN-3D Boiling Models against Experimental Subcooled Boiling Tube Data
Nuclear Technology, Vol. 142, 47-63 (2003)

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2002

ANALYTIS G.TH., CODDINGTON P.
Analysis and sensitivity studies of postulated SB-LOCAs in the Mühleberg (KKM) BWR/4 by TRAC-BF1
Annals of Nuclear Energy, 29, 1525-1549 (2002)

BEHRINGER K., HENNIG D.
A novel auto-correlation function method for the determination of the decay ratio in BWR stability analysis
Annals of Nuclear Energy, 29, 1483-1504 (2002)

CODDINGTON P., MACIAN R.
A study of the performance of void fraction correlations used in the context of drift-flux two-phase flow models
Nuclear Engineering and Design, 215, 199-216

CODDINGTON P., MACIAN R., ZIMMERMANN M.A., CHAWLA R.
Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients
Journal of Nuclear Science and Technology, 39-9, 972-985 (2002)

MACIAN R., CODDINGTON P.
Simulation and Analysis of Experimental Blow down and Small-Break Loss-of-Coolant Scenarios with RETRAN-3D
Nuclear Technology, Vol. 139, 185-204 (2002)

MIRO R., GINESTAR D., VERDU G., HENNIG D.
A nodal modal method for the neutron diffusion equation. Application to BWR stability analysis
Annals of Nuclear Energy, 29, 1171-1194 (2002)

PELLONI S., CHAWLA R.
On the Feasibility of ADS-Representative Integral Experiments Using Limited Amounts of Low-Enriched U-Fuel
Journal of Nuclear Science and Technology, Supplement 2, 1224-1227 (2002)

PELLONI S., HAGER H., JONEJA O.P., CHAWLA R.
Data Sensitivity of Design Calculations for High Conversion D2O Reactors
Journal of Nuclear Science and Technology, Supplement 2, 880-883 (2002)

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2001

ANALYTIS G. TH., HENNIG D., H. KARLSSON K.-H.
The Physical Mechanism of Core-Wide and Local Instabilities at the Forsmark-1 BWR
Nuclear Engineering and Design, Vol. 205, pp. 91-105, 2001.

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2000

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1999

R. Macian, P. Cebull, P. Coddington, M. Paulsen
Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN-3D
PSI Annual Report 1998, Annex IV, ISSN 1423-7334, (1999)

D. Hennig
A Study of Boiling water Reactor Stability Behaviour
Nucl. Technology, Vol. 126, pp 10-31, (1999)

R. Macian, P. Cebull, P. Coddington, M. Paulsen
Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN-3D
Nucl. Technology, Vol. 128, pp 139-152, (1999)

D. Maier, P. Coddington
Evaluation of the Slip Option in RETRAN-3D
Nucl. Technology, Vol. 128, pp 153-168, (1999)

Y. Aounallah, P. Coddington
VIPRE-02 Subchannel Validation Against NUPEC BWR Void Fraction Data
Nucl. Technology, Vol. 128, pp 225-232, (1999)

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1997

P. Coddington
Analysis of BWR6/Start-Up Tests with RETRAN and TRAC
PSI Annual Report 1997 / Annex IV

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1996

D. Hennig
A Challenge for the Study of Complex Nonlinear Dynamical Systems, Boiling Water Reactor Stability Analysis
PSI Annual Report 1996, Annex IV, p. 33-43

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1995

Holzgrewe F., J.M. Kallfelz, M.A. Zimmermann
Investigations Related to Increased Safety Requirements for Reactivity Initiated Accidents
PSI Annual Report 1995, Annex IV, p. 9-14. (1995)

J.M. Kallfelz, L.A. Belblidia, P. Grimm
Fuel-Temperature Coefficient for Boiling Water Reactor Transient Calculations: Its Dependence on Reactor Conditions
Nuclear Science and Engineering 121 (1995), 301-311

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1994

A. Galperin, K. Hofer
Integrated Information System for Analysis of Nuclear Power Plants
Nuclear Technology 108, pp. 1-12, (1994)