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Journal Publications



2010

Experiments On Basic Thermalhydraulic Phenomena Relevant For Lwr Containments: Gas Mixing And Transport Induced By Buoyant Jets In A Multi-Compartment Geometry
Zboray Robert, Paladino Domenico
Nuclear Engineering And Design 240, 3158-3169 (2010).
http://dx.doi.org/10.1016/j.nucengdes.2010.05.047

Flow Transport And Mixing Induced By Horizontal Jets Impinging On A Vertical Wall Of The Multi-Compartment Panda Facility
D Paladino, R Zboray, M Andreani, J Dreier
Nuclear Engineering And Design 240, 2054 (2010).
http://dx.doi.org/10.1016/j.nucengdes.2010.03.036

Simulation Of Basic Gas Mixing Tests With Condensation In The Panda Facility Using The Gothic Code
Andreani Michele, Paladino Domenico, George Tom
Nuclear Engineering And Design 240, 1528-1547 (2010).
http://dx.doi.org/10.1016/j.nucengdes.2010.02.021

Simulation Of Gas Mixing And Transport In A Multi-Compartment Geometry Using The Gothic Containment Code And Relatively Coarse Meshes
Andreani Michele, Paladino Domenico
Nuclear Engineering And Design 240, 1506-1527 (2010).
http://dx.doi.org/10.1016/j.nucengdes.2010.02.020

The Panda Tests 9 And 9bis Investigating Gas Mixing And Stratification Triggered By Low Momentum Plumes
Paladino Domenico, Zboray Robert, Auban Olivier
Nuclear Engineering And Design 240, 1262-1270 (2010).
http://dx.doi.org/10.1016/j.nucengdes.2010.01.017

Three-Gas Mixture Plume Inducing Mixing And Stratification In A Multi-Compartment Containment
Paladino Domenico, Zboray Robert, Benz Pascal, Andreani Michele
Nuclear Engineering And Design 240, 210-220 (2010).
http://dx.doi.org/10.1016/j.nucengdes.2008.07.014

Improvements 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,
http://dx.doi.org/10.1016/J.Nucengdes.2010.10.021 (2010)

Vessel Coolant Mixing Effects On A Pwr Main Steam Line Break Transient
O. Zerkak, H. Ferroukhi
Annals of Nuclear Energy, (2010)
http://dx.doi.org/10.1016/J.Anucene.2010.08.016

Performance Of A Monte-Carlo Solution To The H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
A. Vasiliev, H. Ferroukhi, E. Kolbe
Annals of Nuclear Energy 37(2010), Pp. 1404-1410, 2010


Development Of A Wide-Range Pre-Chf Convective Boiling Correlation
Y. Aounallah
Journal of Nuclear Science And Technology, Vol. 47(4), Pp. 357-366, 2010


Analysis Of An Rpv Upper Head Sbloca At The Rosa Facility Using Trace
J. Freixa, A. Manera
Nuclear Engineering And Design, Available Online 30 March, 2010


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


First_principles Study Of Helium Behavior In Nuclear Fuel Materials
Y. Yun, O. Eriksson, P. M. Oppeneer
Chapter 7, Nova Science Publishers, Helium: Characteristics, Compounds And Applications, Isbn:978-1-61761-213-8 (2010)


Main Results Of Phase Iv Bemuse Project. Simulation Of Lbloca In A Npp
M. PéRez, F. ReventóS, L. Batet, R. Pericas, I. Toth, P. Bazin, CréCy. De, Germain. A, Borisov. P, Glaeser. S, Skorek. H, Joucla. T, Probst. J, Ui. P, Chung. A, Oh. B, Y. D, M. Kyncl, R. Pernica, A. Manera, F. D'Auria, A. Petruzzi, Nevo. Del,
Science And Technology of Nuclear Installations (Issn 1687-6075), Vol. 2010, Id 219294 (2010)


Investigating The Esbwr Stability With Experimental And Numerical Tools: A Comparative Study
M. Rohde, C. Marcel, Manera. P, Van. A, Hagen. Der, H. T, J. J, B. Shiralkar
Nuclear Engineering and Des. (Issn 0029-5493), 240(2), 375-384 (2010)


Experimental and calculation results of the integral reflood test QUENCH-14 with M5 (R) cladding tubes
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Annals of Nuclear Energy 37, 1036
http://dx.doi.org/10.1016/j.anucene.2010.04.015

Local nonsimilarity method for the two-phase boundary layer in mixed convection laminar film condensation
Y. Liao, S. Güntay, K. Vierow
International Journal for Heat and Mass Transfer 46, 447
http://dx.doi.org/10.1007/s00231-010-0588-4

Aerosol behavior during SIC control rod failure in QUENCH-13 test
T.M. Lind, A.P. Csordas, I. Nagy, J. Stuckert
Journal of Nuclear Materials 397, 92
http://dx.doi.org/10.1016/j.nucmat.2009.12.013

Implementation of a generalized diffusion layer model for condensation into MELCOR
K. Hogan, Y. Liao, B. Beeny, K. Vierow, R.Jr. Cole, L.L. Humphries, R.O. Gauntt
Nuclear Engineering and Design 240, 3202
http://dx.doi.org/10.1016/j.nucengdes.2010.05.059

De-agglomeration mechanisms of TiO2 aerosol agglomerates in PWR steam generator tube rupture conditions
T.M. Lind, Y. Ammar, A. Dehbi, S. Güntay
Nuclear Engineering and Design 240, 2046
http://dx.doi.org/10.1016/j.nucengdes.2010.03.002

Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR
T.J. Haste, J.C. Birchley, M. Richner
Nuclear Engineering and Design 240, 1599
http://dx.doi.org/10.1016/j.nucengdes.2010.02.006

Influence of corium oxidation on fission product release from molten pool
S.V. Bechta, E.V. Krushinov, S.A. Vitol, V.B. Khabensky, S.Y. Kotova, A.A. Sulatsky, V.V. Gusarov, V.I. Almyashev, G. Ducros, C. Journeau, D. Bottomley, B. Clement, L.E. Herranz, S. Güntay, K. Trambauer, A. Auvinen, V.V. Bezlepkin
Nuclear Engineering and Design 240, 1229
http://dx.doi.org/10.1016/j.nucengdes.2010.01.008

Benchmark study on fuel bundle degradation in the Pebus FPT2 test using state-of-the-art severe accident analysis codes
B. Tóth, A. Bieliauskas, G. Bandini, J.C. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer
Nuclear Technology 169, 81
http://epubs.ans.org/download/?a=9354

Validation against DNS statistics of the normalized Langevin model for particletransport in turbulent channel flows
A. Dehbi
Powder Technology 200, 60
http://dx.doi.org/10.1016/j.powtec.2010.02.009

Monodisperse fine aerosol generation using fluidized bed
T.M. Lind, S. Danner, S. Güntay
Powder Technology 199, 232
http://dx.doi.org/10.1016/j.powtec.2010.01.011

Progress in understanding key aerosol issues
L.E. Herranz, J. Ball, A. Auvinen, D. Bottomley, A. Dehbi, C. Housiadas, P. Piluso, V. Layly, F. Parozzi, M. Reeks
Progress in Nuclear Energy 52, 120
http://dx.doi.org/10.1016/j.pnucene.2009.09.013

Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident
P. Giordano, A. Auvinen, G. Brillant, J. Colombani, N. Davidovich, R. Dickson, T.J. Haste, T. Kärkelä, J.S. Lamy, C. Mun, D. Ohai , Y. Pontillon, M. Steinbrück, N. Vér
Progress in Nuclear Energy 52, 109
http://dx.doi.org/10.1016/j.pnucene.2009.09.011

Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
R. Dubourg, H. Austregesilo, C. Bals, M. Barrachin, J.C. Birchley, T.J. Haste, J.S. Lamy, T.M. Lind, B. Maliverney, C. Marchetto, A. Pinter, M. Steinbrück, J. Stuckert, K. Trambauer, A. Vimi
Progress in Nuclear Energy 52, 97
http://dx.doi.org/10.1016/j.pnucene.2009.09.012

B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments
G. Repetto, O. De Luze, N. Seiler, K. Trambauer, H. Austregesilo, J.C. Birchley, S. Ederli, J.S. Lamy, B. Maliverney, T. Drath, T. Hollands
Progress in Nuclear Energy 52, 37
http://dx.doi.org/10.1016/j.pnucene.2009.09.017

High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
M. Steinbrück, J.C. Birchley, A.V. Boldyrev, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hózer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Vér, M.S. Veshchunov
Progress in Nuclear Energy 52, 19
http://dx.doi.org/10.1016/j.pnucene.2009.07.012

Ranking of severe accident research priorities
B. Schwinges, C. Journeau, T.J. Haste, L. Meyerd, W. Tromm, K. Trambauer
Progress in Nuclear Energy 52, 11
http://dx.doi.org/10.1016/j.pnucene.2009.09.006

SARNET: Severe accident research network of excellence
T. Albiol, J.P. Van Dorsselaere, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Progress in Nuclear Energy* 52, 2
http://dx.doi.org/10.1016/j.pnucene.2009.07.011





2009

Investigations On Mixing Phenomena In Single-Phase Flow In A T-Junction Geometry
C Walker, M Simiano, R Zboray, HM Prassera
Nuclear Engineering And Design 239, 116-126 (2009).
http://dx.doi.org/10.1016/j.nucengdes.2008.09.003

Cfd4nrs With A Focus On Experimental And Cmfd Investigations Of Bubbly Flows
G Yadigaroglu, M Simiano, R Milenkovic, J Kubasch, M Milelli, R Zboray, Cachard De, Smith F, Lakehal B, Sigg D,
Nuclear Engineering And Design 238, 771-785 (2008).
http://dx.doi.org/10.1016/j.nucengdes.2007.02.047

Investigation Of Large-Scale Gas Mixing And Stratification Phenomena Related To Lwr Containment Studies In The Panda Facility
O Auban, R Zboray, D Paladino
Nuclear Engineering And Design 237, 409-419 (2007).
http://dx.doi.org/10.1016/j.nucengdes.2006.07.011

Comprehensive Experimental Investigation Of The Hydrodynamics Of Large-Scale, 3d, Oscillating Bubble Plumes
M Simiano, R Zboray, Cachard de, Lakehal F, Yadigaroglu D,
International Journal Of Multiphase Flow 32, 1160-1181 (2006).
http://dx.doi.org/10.1016/j.ijmultiphaseflow.2006.05.014

Operation Conditions Of A Phase Doppler Anemometer: Droplet Size Measurements With Laser Beam Power, Photomultiplier Voltage, Signal Gain And Signal-To-Noisle Ratio As Parameters
R Kapulla, SB Najera
Measurement Science & Technology 17, 221-227 (2006).
http://dx.doi.org/10.1088/0957-0233/17/1/034

Simulating Large-Scale Bubble Plumes Using Various Closure And Two-Phase Turbulence Models
R Zboray, Cachard de,
Nuclear Engineering And Design 235, 867-884 (2005).
http://dx.doi.org/10.1016/j.nucengdes.2004.11.008

Experimental Investigation Of Natural-Circulation Flow Behavior Under Low-Power/Low-Pressure Conditions In The Large-Scale Panda Facility
O Auban, D Paladino, R Zboray
Nuclear Technology 148, 294-312 (2004).
http://dx.doi.org/10.13182/NT04-A3568

Decobi: Investigation Of Melt Coolability With Bottom Coolant Injection
D Paladino, SA Theerthan, BR Sehgal
Progress In Nuclear Energy 40, 161-206 (2002).
http://dx.doi.org/10.1016/S0149-1970(01)00022-1

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


Study Of The Pwr Rea Pulse Width For Realistic Uo2 And Mox Core Designs Using 3-D Kinetics
H. Ferroukhi, M.A. Zimmermann
Annals of Nuclear Energy, Volume 36, Issue 8, Pp. 1170-1183, August 2009


Single-Phase Mixing Studies By Means Of A Directly Coupled Cfd/System-Code Tool
D. Bertolloto, A. Manera, S. Frey, H-M. Prasser, R. Chawla
Annals of Nuclear Energy, Volume 36, Issue 3, Pp 310-316 , April 2009


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, Volume 36, Issue 3, Pp 286-291 , April 2009


Advanced Microchannel Heat Exchanger With S-Shaped Fins
N. Tsuzuki, Y. Kato, K. Nikitin, T. Ishizuka
Journal of Nuclear Science And Technology, 46(5), 403-412 (2009)


Comparison Between Wire-Mesh Sensors And Conductive Needle-Probes For Measurements Of Two-Phase Flow Parameters
A. Manera, B. Ozar, S. Paranjape, M. Ishii, H. Prasser,
Nuclear Engineering and Des. (Issn 0029-5493), 239(9), 1718-1724 (2009)


Sbloca With Boron Dilution In Pressurized Water Reactors. Impact On Operation And Safety
J. Freixa, F. ReventóS, C. Pretel, L. Batet, I. Sol
Nuclear Engineering and Des. (Issn 0029-5493), 239(4), 749-760 (2009)


AgInCd control rod failure in the QUENCH-13 bundle test
L. Sepold, T.M. Lind, A.P. Csordas, U. Stegmaier, M. Steinbrück, J. Stuckert
Annals of Nuclear Energy 36, 1349
http://dx.doi.org/10.1016/j.anucene.2009.06.020

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle
J. Stuckert, J.C. Birchley, M. Große, T.J. Haste, L. Sepold, M. Steinbrück
Annals of Nuclear Energy* 36, 183
http://dx.doi.org/10.1016/j.anucene.2008.11.024

Transition from natural to mixed convection for steam-gas flow condensing along a vertical plate
Y. Liao, K. Vierow, A. Dehbi, S. Güntay
International Journal for Heat and Mass Transfer 52, 366
http://dx.doi.org/10.1016/j.ijheatmasstransfer.2008.06.008

A stochastic Langevin model of turbulent particle dispersion in the presence of thermophoresis
A. Dehbi
International Journal of Multiphase Flow 35, 219
http://dx.doi.org/10.1016/j.ijmultiphaseflow.2009.11.006

Reflux condensation of flowing vapor and non-condensable gases counter-current to laminar liquid film in a vertical tube
Y. Liao, S. Güntay, D.J. Suckow, A. Dehbi
Nuclear Engineering and Design 239, 2409
http://dx.doi.org/10.1016/j.nucengdes.2009.07.006

Potential steam generator tube rupture in the presence of severe accident thermal challenge and tube flaws due to foreign object wear
Y. Liao, S. Güntay
Nuclear Engineering and Design 239, 1128
http://dx.doi.org/10.1016/j.nucengdes.2009.02.003

Separate-effect tests on zirconium cladding degradation in air ingress situations
C. Duriez, M. Steinbrück, D. Ohai, T. Meleg, J.C. Birchley, T.J. Haste
Nuclear Engineering and Design 239, 244
http://dx.doi.org/10.1016/j.nucengdes.2008.10.017





2008

A Separate-Effect-Based New Appraisal Of Convective Boiling And Its Suppression
Y. Aounallah
Journal of Nuclear Sci. And Techn. (Issn 0022-3131), 45(2), 149-159 (2008)


One- And Two-Dimensional Standing Pressure Waves And One-Dimensional Travelling Pulses Using The Us-Nrc Nuclear Systems Analysis Code Trace
W. Barten, A. Manera A., R. Macian-Juan
Nuclear Engineering and Des. (Issn 0029-5493), 238, 2568-2582 (2008)


Analysis Of The Capability Of System Codes To Model Cavitation Water Hammers: Simulation Of Umsicht Water Hammer Experiments With Trace And Relap5
W. Barten, A. Jasiulevicius, A. Manera, R. Macian-Juan, O. Zerkak
Nuclear Engineering and Des. (Issn 0029-5493), 238, 1129-1145 (2008)


Consistent Evaluation Of Modern Nuclear Data Libraries For Criticality Safety Analyses Of Thermal Compound Low-Enriched-Uranium Systems
E. Kolbe, A. Vasiliev, H. Ferroukhi, M.A. Zimmermann
Annals of Nuclear Energy (Issn 0306-4549), 35, 1831-1841 (2008)


Towards The Development Of Upper Subcriticality Limits On The Basis Of Benchmark Criticality Calculations
A. Vasiliev, E. Kolbe, M.A. Zimmermann
Annals of Nuclear Energy (Issn 0306-4549), 35, 1831-1841 (2008)


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 (Issn 0306-4549), 35, 565-569 (2008)


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 (Issn 0306-4549), 35, 2432-2435 (2008)


Interpretation Of High-Burnup Fuel Annealing Tests
P. Blair, G. Khvostov, A. Romano, C. Hellwig, R. Chawla
J. of Nuclear Sci. And Techn. (Issn 0022-3131), 45(7), 639-646 (2008)


A Generalized Mean Temperature Difference Method For Thermal Design Of Heat Exchangers
M. Utamura, K. Nikitin, Y. Kato
Ijnest, 4(1), (2008)


Steam Condensing Liquid Co2 Boiling Heat Transfer In A Steam Condenser For A New Heat Recovery System
K. Nikitin, Y. Kato, T. Ishizuka
International Journal of Heat And Mass Transfer, 51(17/18), 4544-4550 (2008)


Uncertainty And Sensitivity Analysis Of The Loft L2-5 Test: Results Of The Bemuse Programme
De CréCy A., Bazin P., Glaeser H., Skorek T., Joucla J., Probst P., Fujioka K., Chung B.D., Oh D.Y., Kyncl M., Pernica R., Macek J., Meca R., Macian R., D’Auria F. Petruzzi A. Bater L., Perez M., Reventos F.
Nuclear Engineering and Des. (Issn 0029-5493), 238, 3561-3578 (2008)


Modeling The Hydrogen Storage Materials With Exposed M2+ Coordination Sites
M. Kosa, M. Krack, A. Cheetham, Parrinello. K,
J. Phys. Chem C (Issn 1932-7447), 112, 16171-16173 (2008)


X-Ray Absorption Spectra Of Hexagonal Ice And Liquid Water By All-Electron Gaussian And Augmented Plane Wave Calculations
M. Iannuzzi-Mauri
J. Chem. Phys. (Issn 0021-9606), 128, 204506-204506-12 (2008)


First-Principles Molecular Dynamics Study Of The Heterogeneous Reduction Of No2 On Soot Surfaces
Rodriguez-Fortea A., Iannuzzi Mauri M.
J. Phys. Chem C (Issn 1932-7447), 112, 19642-19648 (2008)


Modeling Bulk And Surface Pt Using The “Gaussian And Plane Wave” Density Functional Theory Formalism: Validation And Comparison To K-Point Plane Wave Calculations
G. Santarossa, A. Vargas, Mauri. Iannuzzi, Pignedoli. M, A. C, D. Passerone, A. Baiker
J. Chem. Phys. (Issn 0021-9606), 129, 234703-234703-12 (2008)


Chiral Recognition On Catalytic Surfaces: Theoretical Insight In A Biomimetic Heterogeneous Catalytic System
A. Vargas, G. Santarossa, Mauri. Iannuzzi, Baiker. M,
J. Phys. Chem C (Issn 1932-7447), 112, 10200-10208 (2008)


Turbulent particle dispersion in arbitrary wall-bounded geometries: A coupled CFD-Langevin-equation based approach
A. Dehbi
International Journal of Multiphase Flow 34, 819
http://dx.doi.org/10.1016/j.ijmultiphaseflow.2008.03.001

Effects of chlorine and sulphur on particle formation in wood combustion performed in a laboratory scale reactor
O. Sippula, T.M. Lind, J.K. Jokiniemi
Journal of Fuel 87, 2425
http://dx.doi.org/10.1016/j.fuel.2008.02.004

A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1
A. Rýdl
Nuclear Engineering and Design* 238, 2387
http://dx.doi.org/10.1016/j.nucengdes.2008.02.027

Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR
J.C. Birchley, T.J. Haste, M. Richner
Nuclear Engineering and Design 238, 2173
http://dx.doi.org/10.1016/j.nucengdes.2008.02.009

A CFD model for particle dispersion in turbulent boundary layer flows
A. Dehbi
Nuclear Engineering and Design 238, 707
http://dx.doi.org/10.1016/j.nucengdes.2007.02.055

Validation of severe accident codes on the Phebus fission product tests in the framework of the PHEBEN-2 project
K. Müller, S. Dickinson, C. de Pascale, N. Girault, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, A. Dehbi, S. Paci, F. Martin-Fuentes, I. Turcu, I. Ivanov, B. Toth, L.G. Horvath
Nuclear Technology 163, 209





2007

Bwr Stability And Bifurcatio Analysis Using Reduced Order Models And System Codes: Identification Of A Subcritical Hop Bifurcation Using Ramona
A. Dokhane, D. Hennig, Rizwan-Uddin, R. Chawla
Annals of Nuclear Energy, Volume 34, Issue 10, October 2007, Pp 792-802 (2007)


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, Rizwan-Uddin, R. Chawla
Annals of Nuclear Energy, Volume 34, Issue 4, April 2007, Pp 271-287 (2007)


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, 34(8), Pp 615-627 (2007)


A Statistical Methodology For Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, R. Macian-Juan, R. Chawla
Annals of Nuclear Energy, 34 (8), 628-640 (2007)


Analysis Of The Leibstadt Power Plant Condensate And Feedwater Systems During Selected Operational Transients
O. Zerkak, P. Coddington
Nuclear Science And Engineering, 237(11), 1195-1208 (2007)


Experimental Investigation On Bublbe Turbulent Diffusion In A Vertical Large-Diameter Pipe By Wire-Mesh Sensors And Correlation Techniques
A. Manera, H-M. Prasser, D. Lucas
Nuclear Technology, 158(2), 291-303 (2007)


Fine particle and trace element emissions from waste combustion - Comparison of fluidized bed and grate firing
T.M. Lind, J. Hokkinen, J.K. Jokiniemi
Fuel Processing Technology 88, 737
http://dx.doi.org/10.1016/j.fuproc.2007.03.004

Radiochemical studies of the retention of volatile iodine in aqueous solutions
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Journal of Radioanalytical and Nuclear Chemistry 273, 557
http://dx.doi.org/10.1007/s10967-007-0909-3

Major challenges to modeling aerosol retention near a tube breach during steam generator tube rupture sequences
L.E. Herranz, C. Lopez del Pra, A. Dehbi
Nuclear Technology 158, 83


Benchmark study on fuel bundle degradation in the Phebus FPT3 test using the severe accident codes ATHLET-CD, ICARE2, and MELCOR
B. Toth, K. Müller, J.C. Birchley, H. Wada, C. Jamond, K. Trambauer
Nuclear Technology 157, 132





2006

Retran-3d Analysis Of The Base Case And The Four Extreme Cases Of The Oecd/Nea Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington, H. Ferroukhi
Annals of Nuclear Energy 33, Pp 99-118 (2006)


Spatial And Model-Order Based Reactor Signal Analysis Methodolgy For Bwr Core Stability Evaluation
A. Dokhane, H. Ferroukhi, M.A. Zimmermann, C. Aguirre
Annals of Nuclear Energy, Volume 33, Issue 16, November 2006, Pp 1329-1338 (2006)


Modeling 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 Des. (Issn 0029-5493), 236, 284-294 (2006)


Calculations On Fission Gas Behaviour In The High Burnup Structure
P. Blair, A. Romano, C. Hellwig, R. Chawla
J. Nuclear Mater. (Issn 0022-3115), 350, 232-239 (2006)


Investigations On The Stability Of The Flow Characteristics In A Bubble Column
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Chem. Engineering and Technol. (Issn 1521-4125), 9, 1066-1072 (2006)


Implications Of Alternative Strategies For Transitions To Sustainable Fuel Cycles
A. Romano, T. Boscher, P. Hejzlar, M. Kazimi, N. Todreas
Nuclear Sci. Engineering and (Issn 0029-5639), 154, 1-27 (2006)


Atomistic Simulation Of Rapid Compression Of Fractured Silicon Carbide
A. Romano, J. Li, S. Yip
J. Nuclear Mater. (Issn 0022-3115), 352, 22-28 (2006)


Effect of chlorine and sulfur on fine particle formation in pilot-scale CFBC of biomass
T.M. Lind, E.L. Kauppinen, J. Hokkinen, J.K. Jokiniemi, M. Orjala, M. Aurela, R. Hillamo
Energy and Fuels 20, 61
http://dx.doi.org/10.1021/ef050122i

Electrostatic precipitator performance and trace element emissions from two Kraft recovery boilers
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, R. Hillamo, U. Makkonen, A. Raukola, J. Rintanen, K. Saviharju
Environmental Science & Technology 40, 584
http://dx.doi.org/10.1021/es0503027

MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences
T.J. Haste, J.C. Birchley, E.G. Cazzoli, J. Vitazkova
Nuclear Engineering and Design 236, 1099
http://dx.doi.org/10.1002/j.nucengdes.2005.11.012

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