Conference Publications 2014

Assessment Of Trace Against Single-Tube Post-Dryout Heat Transfer Experiments
Y. Aounallah
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Post-Test Analysis Of Oecd/Nea Rosa-2 Test 4 Using Trace
I. Clifford, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Uncertainty And Sensitivity Analysis Of Cobra-Tf For The Simulation Of Selected Oecd/Nrc Bfbt Void Experiments
A. Epiney, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Assessment Of Cfd Urans Models For Buoyancy Driven Mixing Flows Based On Rocom Experiments
R. Puragliesi, O. Zerkak And A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Treatment Of Epistemic And Aleatory Uncertainties In Det Simulations: Computational Framework With Ads-Trace
S. Rahman, D.R. Karanki, O. Zerkak, V.N. Dang
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Exploring Variability In Reflood Simulation Results: An Application Of Functional Data Analysis
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Sensitivity Analysis Of A Bottom Reflood Simulation Using The Morris Screening Method
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014


Analysis Of The Oecd/Nea Oskarshamn-2 Feedwater Transient And Stability Benchmark With Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Uncertainty And Sensitivity Study Of Fuel Thermal Behaviour Within Oecd/Nea Uam Programme
Y. Yun, C. Cozzo, O. Leray, H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Nuss-Rf: Stochastic Sampling-Based Tool For Nuclear Data Sensitivity And Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Stochastic Sampling-Based Tool For Nuclear Data Sensitivity Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Youth. Nucl. Congress Iync2014, Burgos, Spain, July 6-12, 2014


Uncertainty Quantification Of Spent Fuel Nuclide Compositions Due To Cross-Sections, Decay Constants And Fission Yields
O. Leray, P. Grimm, M. Hursin, H. Ferroukhi And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Quantification Of Code. Library And Cross-Section Uncertainty Effects On The Void Reactivity Coefficient Of A Bwr Uo2 Assembly
O. Leray, P. Grimm, H. Ferroukhi, And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Effects Of Advanced Radial Submeshing Methods On Pin Power Reconstruction For An Epr Core Design
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


New Psi Methodology For Manufacturing And Technological Uncertainty Quantification
M. Pecchia, A. Vasiliev, O. Leray, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Updated Validation Of The Psi Criticality Safety Evaluation Methodology Using Mcnpx2.7 And Endf/B-Vii.1
M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Validation Of Two Monte Carlo Codes For Lwr Burnup Calculations
D. Wicaksono, P. Grimm, A.Vasiliev, M. Hursin, G. Perret, And H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014


Analysis Of Axial Fuel Relocation Based On Gamma Scan Data From Oecd Halden Reactor Project Loca Tests
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Water Reactor Fuel Performance Meeting Wrfpm2014, Sendai, Japan, September 14-17, 2014


Fuel Relocation In Ifa-650 Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Enlarged Halden Project Group Meeting, Roeso, Norway, September 7-12, 2014


Reactivity Benchmark Analysis And Code Reactivity Prediction For A Pwr Fuel Assembly
H. Perrier, O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013


Neutronic Data Generation For Bwr Models, Comparison Of Serpent And Casmo-5
L. Rossinelli, M. Hursin. H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013


Validation Enhancements Of The Psi Fast Neutron Fluence Computational Scheme Using Operational Pwr Experimental Data
A. Dupre, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013

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