Journal Publications 2011
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)
Assessment Of The Jeff-3.1.1 Neutron Data Library For Cse Of Lwr Fuel Storage Pools
E. Kolbe, A. Vasiliev, H. Ferroukhi
Journal of The Korean Nuclear Society, Vol. 59, Pp. 1174-1178 (2011)
Refined Monte Carlo Analysis Of The H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark
R. Pittarello, A. Vasiliev, H. Ferroukhi, R. Chawla
Annals of Nuclear Energy, Vol. 38, Pp. 1842-1851 (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)
A Model For Fission Gas Release And Gaseous Swelling Of The Uranium Dioxide Fuel Coupled With The Falcon Code
G. Khvostov
Nuclear Engineering And Design, Vol. 241, Pp 2983-3007 (2011)
Some Insights Into The Role Of Axial Gas Flow In Fuel Rod Behaviour During The Loca Based On Halden Tests And Calculations With The Falcon-Psi Code
G. Khvostov, W. Wiesenack, M.A. Zimmermann, G. Ledergerber
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1500-1507 (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
Nuclear Engineering And Design, Vol. 241, Issue 3, Pp 815-825, March 2011
Assessment Of Fuel Rod Performance Codes Under Ramp Scenarios Investigated Within The Scip Project
(Sb-Xtk-Act-003-07.004)
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)
V. Petrov, A. Manera
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1476-1485 (2011)
Assessment Of The Jeff-3.1.1 Neutron Data Library For Cse Of Lwr Fuel Storage Pools
E. Kolbe, A. Vasiliev, H. Ferroukhi
Journal of The Korean Nuclear Society, Vol. 59, Pp. 1174-1178 (2011)
Refined Monte Carlo Analysis Of The H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark
R. Pittarello, A. Vasiliev, H. Ferroukhi, R. Chawla
Annals of Nuclear Energy, Vol. 38, Pp. 1842-1851 (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)
A Model For Fission Gas Release And Gaseous Swelling Of The Uranium Dioxide Fuel Coupled With The Falcon Code
G. Khvostov
Nuclear Engineering And Design, Vol. 241, Pp 2983-3007 (2011)
Some Insights Into The Role Of Axial Gas Flow In Fuel Rod Behaviour During The Loca Based On Halden Tests And Calculations With The Falcon-Psi Code
G. Khvostov, W. Wiesenack, M.A. Zimmermann, G. Ledergerber
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1500-1507 (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
Nuclear Engineering And Design, Vol. 241, Issue 3, Pp 815-825, March 2011
Assessment Of Fuel Rod Performance Codes Under Ramp Scenarios Investigated Within The Scip Project
(Sb-Xtk-Act-003-07.004)
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)
