Journal publications of the STARS Program

Our scientists, post docs and students regularly publish articles in scientific magazines primarily in the nuclear engineering and technical field. For this purpose, each submitted article is first thoroughly reviewed and then approved.  

Here you will find a selection of journals that regularly publish articles from our laboratory:
 

• Nuclear Engineering and Technology
• Nuclear Engineering and Design
• Annals of Nuclear Energy
• EPJ Nuclear Scientific Technologies
• Neural Computing and Applications
• Progress in Nuclear Energy
• Experimental Thermal and Fluid Science
• Physical Review Letters

>>Back to top

>>Back to top

>>Back to top

>>Back to top

>>Back to top

Seidl M, Schillebeeckx P, Rochman D

On the potential to increase the accuracy of source term calculations for spent nuclear fuel from an industry perspective
atw Int. J. Nucl. Power. 2020:353-361.
DORA PSI

>>Back to top

Kromer H, Adams R, Soubelet B, Zboray R, Prasser H-M
Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
Applied Radiation and Isotopes. 2019; 145: 47-54. 
https://doi.org/10.1016/j.apradiso.2018.12.009
DORA PSI

Papini D, Andreani M, Steiner P, Ničeno B, Klügel J-U, Prasser H-M
Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Nuclear Technology. 2019; 205(1-2): 153-173. 
https://doi.org/10.1080/00295450.2018.1505356
DORA PSI

Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
Radiation Physics and Chemistry. 2019; 156: 292-299. 
https://doi.org/10.1016/j.radphyschem.2018.11.017
DORA PSI

>>Back to top

Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
N_TOF Collaboration including D. Rochman
EPJ Web of Conferences 178, 03004 (2018)
https://doi.org/10.1051/epjconf/201817803004

Technical note: On modeling central void formation in LWR fuel pellets due to hightemperature restructuring
G. Khvostov
Nuclear Engineering and Design
https://doi.org/10.1016/j.net.2018.07.003
 

>>Back to top

SFCOMPO-2.0: An OECD NEA Database Of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, And Operating Data
F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, K. Govers, M. Gysemans, V. Hannstein, F. Havlu, M. Hennebach, G. Hordosy, G. Ilas, R. Kilger, R. Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. RantamäKi, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, S. Van Winckel, A. Vasiliev, T. Watanabe, Toru Yamamoto, Toshihisa Yamamoto
Annals of Nuclear Energy 110 (2017) 779 788
http://dx.doi.org/10.1016/j.anucene.2017.07.022

Modelling And Analysis Of Selected OECD PKL3 Station-Blackout Experiments Using TRACE
R. Mukin, I. Clifford, O. Zerkak, H. Ferroukhi
Nuclear Engineering and Technology, Net 473. (2017)
https://doi.org/10.1016/j.net.2017.12.005

>>Back to top

Steady-State CFD Simulations Of An Eprtm Reactor Pressure Vessel: A Validation Study Based On The Juliette Experiments
R. Puragliesi, L. Zhou, O. Zerkak, A. Pautz
Nuclear Engineering And Design, Vol. 300, Pp. 41 56 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.12.025

>>Back to top

A Dynamic Event Tree Informed Approach To Probabilistic Accident Sequence Modeling: Dynamics And Variabilities In Medium LOCA
D.R. Karanki, T-W. Kim, V.N. Dang
Reliability Engineering And System Safety, Vol. 142, Pp. 78 91 (2015)
http://dx.doi.org/10.1016/j.ress.2015.04.011

Gen-Foam: A Novel Openfoam Based Multi-Physics Solver FOR2d/3d Transient Analysis Of Nuclear Reactors
C. Fiorina, I. Clifford, M. Aufiero, K. Mikityuk
Nuclear Engineering And Design, Vol. 294, Pp. 24-37, (2015)

Boron Dilution Transient Simulation Analyses In A PWR With Neutronics/Thermal-Hydraulics Coupled Codes In The NURISP Project
G. Jimenez, J.J. Herrero, A. Gommlich, S. Kliem, D. Cuervo, J. Jimenez
Annals of Nuclear Energy Vol. 84, Pp. 86-97 (2015)

Review Of Multi-Physics Temporal Coupling Methods For Analysis Of Nuclear Reactors
O. Zerkak, T. Kozlowski, I. Gajev
Annals of Nuclear Energy Vol. 84, Pp. 225-233 (2015)

Modelling Guidelines For Core Exit Temperature Simulations With System Codes
J. Freixa V. MartíNez-Quiroga, O. Zerkak, F. ReventóS
Nuclear Engineering and Design, Vol. 286, Pp. 116-129 (2015)

>>Back to top

Assessment Of GOTHIC And TRACE Codes Against Selected Panda Experiments On A Passive Containment Condenser
D. Papini, C. Adamsson, M. Andreani, H-M. Prasser
Nuclear Engineering and Design, Vol. 278, Pp. 542-557 (2014)

Post-Test Thermal-Hydraulic Analysis Of Two Intermediate LOCA Tests At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, W-W. Kim, A. Manera
Nuclear Engineering And Design, Vol. 264, Pp 153-160 (2013)
http://dx.doi.org/10.1016/j.nucengdes.2013.02.023

Large Eddy Simulation Of The Differentially Heated Cubic Cavity Flow By The Spectral Element Method
C. Bosshard, A. Dehbi, E. Leriche, R. Puragliesi, A. Soldati
Computers And Fluids, Vol. 86, Pp. 210-227 (2013)

Simulation Of Halden IFA-650 Loss-Of-Coolant Accidents Tests With TRACE
Y. Aounallah
Kerntechnik, Vol 77, Pp 316-323 (2012)

Analysis Of The Isp-50 Direct Vessel Injection Sbloca In The ATLAS Facility Witth The RELAP5/MOD3.3 Code
M. Sharabi, J. Freixa
Nuclear Engineering And Technology, Vol. 44, Pp 709-718 (2012)

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

Quantitative Evaluation Of Change In Core Damage Frequency By Postulated Power Uprate: Medium-Break Loss-Of-Coolant-Accidents
T-W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Annals of Nuclear Energy, Vol. 47, September 2012, Pp. 69-80 (2012)

Remarks On Consistent Development Of Plant Nodalizations: An Example Of Application To The Rosa Integral Test Facility
J. Freixa, A. Manera
Science And Technology of Nuclear Installations, Vol. 2012, Article Id 158617 (2012)

Effect Of Pump-Induced Cold-Leg Swirls On The Flow Field In The RPV Of The EPR - CFD Investigations And Comparison With Experimental Results
V. Petrov, A. Manera
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1476-1485 (2011)

Analysis Of An Ads Spurious Opening Event At A BWR/6 By Means Of The TRACE Code
K. Nikitin, A. Manera
Nuclear Engineering And Design, Doi: 10.1016/J.Nucengdes2011.03.021 (2011)

Verification Of A TRACE EPR Model On The Basis Of A Scaling Calculation Of An SBLOCA Rosa Test
J. Freixa, A. Manera
Nuclear Engineering And Design, Volume 241, Issue 3, March 2011, P 888-896 (2011)

Uncertainty And Sensitivity Analysis Of A LBLOCA In A PWR Nuclear Power Plant: Results Of The Phase V Of The Bemuse Programme
M. Perez, F. Reventosa, L. Batet, A. Guba, I. TóTh, T. Mieusset, P. Bazin, A. De CréCy, S. Borisov, T. Skorek, H. Glaeser, J. Joucla, P. Probst, A. Ui, B.D. Chung, D.Y. Oh, R. Pernica, M. Kyncl, J. Macek, A. Manera, J. Freixa, A. Petruzzi, F. D’Auria, A. Del Nevo
Nuclear Engineering And Design, Vol. 241, Issue 10, Pp 4206-4222, October 2011

Modeling And Validation Of A Mechanistic Tool (Mefisto) For The Prediction Of Critical Power In BWR Fuel Assemblies
C. Adamsson, J-M. Le Corre
Nuclear Engineering And Design, Vol. 241, Issue 8, Pp 2843-2858, August 2011

First_principles Investigation Of Higher Oxides Of Uranium And Neptunium: U3o8 And Np20
Y. Yun, J. Rusz, M-T. Suzuki, P.M. Oppeneer
Physical Review, B 83, 075109, Doi: 10.1103/Phyrevb.83.075109(2011)

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)

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 oca At The Rosa Facility Using TRACE
J. Freixa, A. Manera
Nuclear Engineering And Design, Available Online 30 March, 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 LBLCOA 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)

>>Back to top

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

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)

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)

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)

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)

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)

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)

Semi-Analytical Bifurcation Analysis Of Two-Phase Flow In A Heated Channel
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Int. J. Bifurcation Chaos (Issn 0218-1274), 15, 2395-2409 (2005)

Review Of The Licensing Basis For Ria And Loca Transients In Light Of New Evidence On High Burnup Fuel Behavior
M. Zimmermann, Bart. A,
Chimia (Issn 0009-4293), 59, 950-956 (2005)

>>Back to top

Void Fraction And Critical Power Assessment Of Coretran-01/Vipre-02
Y. Aounallah
Nuclear Technol. (Issn 0029-5450), 145, 163-176 (2004)

Peach Bottom BWR Turbine Trip Benchmark Analyses With Retran-3d And Coretran
W. Barten, H. Ferroukhi, P. Coddington
Nuclear Sci. Engineering and (Issn 0029-5639), 146, 306-324 (2004)

The Analysis Of Pwr And BWR Reactivity Transients With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Nuclear Technology, 142, 19-34 (2003)

Comparison Of Various Partial Light Water Reactor Core Loadings With Inert Matrix And Mixed-Oxide Fuel
U. Kasemeyer, Ch. Hellwig, J. Lebenhaft, R. Chawla
Journal of Nuclear Materials, 319, 142-153 (2003)

Assessment Of Retran-3D Boiling Models Against Experimental Subcooled Boiling Tube Data
R. Macian, P. Coddington, P. Stangroom
Nuclear Technology, Vol. 142, 47-63 (2003)

Interpretation Of Experimental Results From Moderate-Power In-Pile Testing Of A Pu-Er-Zr-Oxide Inert Matrix Fuel
Hellwig Ch., Kasemeyer U., Ledergerber G., Byung-Ho Lee, Young-Woo Lee, Chawla R.
Annals of Nuclear Energy 30, 287-299 (2003)

Planned Experimental Studies On Natural Circulation And Stability Performance Of Boiling Water Reactors In Four Experimental Facilities And First Results (Nacusp)
De Kruijf W.J.M., Katelaar K.C.J, Avakian G., Gubernatis P., Caruge D., Manera A., Van Der Hagen T.H.J.J., Yadigaroglu G., Domenicus G., Rohde U., Prasser H.-M., Castrillo F., Huggenberger M., Hennig D., Munoz-Cobo J.L., Aguirre C.
Nuclear Engineering And Design, 221, 241-250 (2003)

Analysis And Sensitivity Studies Of Postulated Sb-Locas In The Mühleberg (Kkm) BWR/4 By Trac-Bf1
G. Analytis, Coddington. Th,
Annals of Nuclear Energy, 29, 1525-1549 (2002)

Core loss during a severe accident (COLOSS)
B. Adroguer, P. Chatelard, J.P. van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Müller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G. Bandini, J.C. Birchley, T. von Berlepsch, M. Buck, J.A.F. Benitez, E. Virtanen, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev
Nuclear Engineering and Design 221, 55
http://dx.doi.org/10.1016/S0029-5493(02)00344-8

A Novel Auto-Correlation Function Method For The Determination Of The Decay Ratio In BWR Stability Analysis
K. Behringer, D. Hennig
Annals of Nuclear Energy, 29, 1483-1504 (2002)

A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Nuclear Engineering And Design, 215, 199-216

Application And In-Depth Assessment Of Retran-3d For Best Estimate Analysis Of Nuclear Power Plant Transients
P. Coddington, R. Macian, M. Zimmermann, Chawla. A,
Journal of Nuclear Science And Technology, 39-9, 972-985 (2002)

Simulation And Analysis Of Experimental Blow Down And Small-Break Loss-Of-Coolant Scenarios With Retran-3D
R. Macian, P. Coddington
Nuclear Technology, Vol. 139, 185-204 (2002)

A Nodal Modal Method For The Neutron Diffusion Equation. Application To BWR Stability Analysis
R. Miro, D. Ginestar, G. Verdu, D. Hennig
Annals of Nuclear Energy, 29, 1171-1194 (2002)

On The Feasibility Of Ads-Representative Integral Experiments Using Limited Amounts Of Low-Enriched U-Fuel
S. Pelloni, R. Chawla
Journal of Nuclear Science And Technology, Supplement 2, 1224-1227 (2002)

Data Sensitivity Of Design Calculations For High Conversion D2o Reactors
S. Pelloni, H. Hager, O. Joneja, Chawla. P,
Journal of Nuclear Science And Technology, Supplement 2, 880-883 (2002)

The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 BWR
G. Analytis, Hennig. Th, H. D, K. Karlsson,
Nuclear Engineering And Design, Vol. 205, Pp. 91-105, 2001.

>>Back to top

A Study Of Boiling Water Reactor Stability Behaviour
D. Hennig
Nuclear Technology, Vol. 126, Pp 10-31, (1999)

Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Nuclear Technology, Vol. 128, Pp 139-152, (1999)

Evaluation Of The Slip Option In Retran-3d
D. Maier, P. Coddington
Nuclear Technology, Vol. 128, Pp 153-168, (1999)

Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Nuclear Technology, Vol. 128, Pp 225-232, (1999)

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

>>Back to top