Conference Publications 2017

Sic Caldding Behaviour: Experiments And Modelling At Psi
C. Cozzo, J. Bertsch, L. Fave, S. Rahman, A. Dokhane, M. Krack, M.A. Pouchon, Y. Dai, J-C. Chen, M. Pytel
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017


New Insights In The Fuel Grain Subdivision During In-Plant Irraditaion Up To High Burnup
M. Chollet, C. Cozzo, J. Bertsch, M. Martin, D. Grolimund, V-A. Samson
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017


Thermal Mixing Assessment Using 3d Thermal-Hydraulic And Cfd Codes
R. Mukin, R. Puragliesi, S. C. Ceuca, H. Austregesilo, A. Bousbia Salah
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017


Thermal Hydraulic Analysis Of Pwr Assembly Bowing Using Subchannel Code Cobra-Tf
R. Mukin, I. Clifford, H. Ferroukhi, M. Seidl
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017


Characterization Of The Energy-Dependent Uncertainty And Correlation In Silicon Neutron Displacement Damage Metrics
P. Griffin, D. Rochman, A. Koning
Epj Web of Conferences 146, 02008, Nd2016 (2017)


Talys/Tendl Verification And Validation Processes: Outcomes And Recommendations
M. Fleming, J-C. Sublet, M. R. Gilbert, A. Koning, D. Rochman
Epj Web of Conferences 146, 02033, (2017)


Propagation Of Nuclear Data Uncertainties For Fusion Power Measurements
H.Sjostrand, S. Conroy, P. Helgesson, S. A. Hernandez, A. Koning, S. Pomp, D. Rochman
Epj Web of Conferences 146, 02034 (2017)


The Role Of Nuclear Data For Fusion Nuclear Technology
U. Fischer, M. Angelone, M. Avrigeanu, V. Avrigeanu, C. Bachmann, N. Dzysiuk, M. Fleming, A. Konobeev, I. Kodeli, A. Koning, H. Leeb, D. Leichtle, F. Ogando, P. Pereslavtsev, D. Rochman, P. Sauvan, S. Simakov
Proc. Int. Conf. Fusion Nuclear Technology Conference, Kyoto, September 25 -29, 2017


Trace/S3k Code Coupling Simulations Of A Bwr/4 Anticipated Transient Without Scram
Y. Aounallah
Proc. Canadian Nuclear Soeciety Meeting Niagara Falls, Canada, June 4-7, 2017


Simulations With Trace Of A Bwr/4 Steam Line Break Under Hot Standby Conditions
Y. Aounallah
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017


Simulate-3k Analyses Of Neutron Noise Response To Fuel Assembly Vibrations And Thermal-Hydraulics Parameters Fluctuations
D. Chionis, A. Dokhane, L. Belblidia, M. Pecchia, G. Girardin, H. Ferroukhi, A. Pautz
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017


Nodal And Pin-By-Pin Calculations Comparison With Codes Simulate-5 And Dyn3d
P. Mala, A. Pautz, S. Canepa, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017


Bowing Effects On Power And Burn-Up Distributions For Simplified Full Pwr And Bwr Cores
D. Rochman, P. Mala, H. Ferroukhi, A. Vasiliev, M. Seidl, D. Janin, J. Li
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017


Nuclear Data Uncertainty Decomposition For Spert-Iii Ria Experiments Using Simulate-3k And Shark-X
A. Dokhane, G. Grandi, O. Leray, D. Rochman, A. Vasiliev, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017

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